Sample records for munitions waste working
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Military Munitions Waste Working Group report
International Nuclear Information System (INIS)
1993-01-01
This report presents the findings of the Military Munitions Waste Working Group in its effort to achieve the goals directed under the Federal Advisory Committee to Develop On-Site Innovative Technologies (DOIT Committee) for environmental restoration and waste management. The Military Munitions Waste Working Group identified the following seven areas of concern associated with the ordnance (energetics) waste stream: unexploded ordnance; stockpiled; disposed -- at known locations, i.e., disposal pits; discharged -- impact areas, unknown disposal sites; contaminated media; chemical sureties/weapons; biological weapons; munitions production; depleted uranium; and rocket motor and fuel disposal (open burn/open detonation). Because of time constraints, the Military Munitions Waste Working Group has focused on unexploded ordnance and contaminated media with the understanding that remaining waste streams will be considered as time permits. Contents of this report are as follows: executive summary; introduction; Military Munitions Waste Working Group charter; description of priority waste stream problems; shortcomings of existing approaches, processes and technologies; innovative approaches, processes and technologies, work force planning, training, and education issues relative to technology development and cleanup; criteria used to identify and screen potential demonstration projects; list of potential candidate demonstration projects for the DOIT committee decision/recommendation and appendices
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Military Munitions Waste Working Group report
Energy Technology Data Exchange (ETDEWEB)
1993-11-30
This report presents the findings of the Military Munitions Waste Working Group in its effort to achieve the goals directed under the Federal Advisory Committee to Develop On-Site Innovative Technologies (DOIT Committee) for environmental restoration and waste management. The Military Munitions Waste Working Group identified the following seven areas of concern associated with the ordnance (energetics) waste stream: unexploded ordnance; stockpiled; disposed -- at known locations, i.e., disposal pits; discharged -- impact areas, unknown disposal sites; contaminated media; chemical sureties/weapons; biological weapons; munitions production; depleted uranium; and rocket motor and fuel disposal (open burn/open detonation). Because of time constraints, the Military Munitions Waste Working Group has focused on unexploded ordnance and contaminated media with the understanding that remaining waste streams will be considered as time permits. Contents of this report are as follows: executive summary; introduction; Military Munitions Waste Working Group charter; description of priority waste stream problems; shortcomings of existing approaches, processes and technologies; innovative approaches, processes and technologies, work force planning, training, and education issues relative to technology development and cleanup; criteria used to identify and screen potential demonstration projects; list of potential candidate demonstration projects for the DOIT committee decision/recommendation and appendices.
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40 CFR 266.203 - Standards applicable to the transportation of solid waste military munitions.
2010-07-01
... transportation of solid waste military munitions. 266.203 Section 266.203 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR THE MANAGEMENT OF SPECIFIC HAZARDOUS... applicable to the transportation of solid waste military munitions. (a) Criteria for hazardous waste...
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40 CFR 266.205 - Standards applicable to the storage of solid waste military munitions.
2010-07-01
... solid waste military munitions. 266.205 Section 266.205 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS FOR THE MANAGEMENT OF SPECIFIC HAZARDOUS... applicable to the storage of solid waste military munitions. (a) Criteria for hazardous waste regulation of...
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Computational Modeling of Hydrodynamics and Scour around Underwater Munitions
Liu, X.; Xu, Y.
2017-12-01
Munitions deposited in water bodies are a big threat to human health, safety, and environment. It is thus imperative to predict the motion and the resting status of the underwater munitions. A multitude of physical processes are involved, which include turbulent flows, sediment transport, granular material mechanics, 6 degree-of-freedom motion of the munition, and potential liquefaction. A clear understanding of this unique physical setting is currently lacking. Consequently, it is extremely hard to make reliable predictions. In this work, we present the computational modeling of two importance processes, i.e., hydrodynamics and scour, around munition objects. Other physical processes are also considered in our comprehensive model. However, they are not shown in this talk. To properly model the dynamics of the deforming bed and the motion of the object, an immersed boundary method is implemented in the open source CFD package OpenFOAM. Fixed bed and scour cases are simulated and compared with laboratory experiments. The future work of this project will implement the coupling between all the physical processes.
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40 CFR 266.202 - Definition of solid waste.
2010-07-01
... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Definition of solid waste. 266.202 Section 266.202 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES... MANAGEMENT FACILITIES Military Munitions § 266.202 Definition of solid waste. (a) A military munition is not...
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Directory of Open Access Journals (Sweden)
Aaron J. Beck
2018-04-01
Full Text Available Coastal marine environments are contaminated globally with a vast quantity of unexploded ordnance and munitions from intentional disposal. These munitions contain organic explosive compounds as well as a variety of metals, and represent point sources of chemical pollution to marine waters. Most underwater munitions originate from World Wars at the beginning of the twentieth century, and metal munitions housings have been impacted by extensive corrosion over the course of the following decades. As a result, the risk of munitions-related contaminant release to the water column is increasing. The behavior of munitions compounds is well-characterized in terrestrial systems and groundwater, but is only poorly understood in marine systems. Organic explosive compounds, primarily nitroaromatics and nitramines, can be degraded or transformed by a variety of biotic and abiotic mechanisms. These reaction products exhibit a range in biogeochemical characteristics such as sorption by particles and sediments, and variable environmental behavior as a result. The reaction products often exhibit increased toxicity to biological receptors and geochemical controls like sorption can limit this exposure. Environmental samples typically show low concentrations of munitions compounds in water and sediments (on the order of ng/L and μg/kg, respectively, and ecological risk appears generally low. Nonetheless, recent work demonstrates the possibility of sub-lethal genetic and metabolic effects. This review evaluates the state of knowledge on the occurrence, fate, and effect of munition-related chemical contaminants in the marine environment. There remain a number of knowledge gaps that limit our understanding of munitions-related contaminant spread and effect, and the need for additional work is made all the more urgent by increasing risk of release to the environment.
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Hawaii Munitions Monitoring Station and Natural Laboratory
Edwards, M.; Trimble, A. Z.; Rognstad, M. R.
2017-12-01
Hundreds of thousands of tons of conventional munitions were fired into the ocean at military ranges or deliberately disposed at sea during the twentieth century. Potential contaminants from munitions and explosives of concern (MEC) affect virtually every coast in the United States, including Alaska, the Hawaiian Islands, Guam, American Samoa and other U.S. territories as well as inland waterways. It is necessary to develop methods to assess the concentrations of munitions constituents present at a site to address concerns about the presence of environmentally relevant concentrations and their potential impacts. Having a well-characterized site to test instruments and methods is important for continued development and refinement of technology. Most sites are too big to characterize comprehensively in three dimensions over time periods lasting days or longer. We are working to develop a monitoring station and natural laboratory near Oahu, Hawaii to create a cost-effective demonstration and validation natural laboratory where emerging technologies can be evaluated and compared. Ordnance Reef (OR) is an ideal location to establish a munitions monitoring station for historical, logistical and environmental reasons. OR is an area of shallow fringing reef measuring approximately 4.2 km by 2.2 km along the Waianae coast of Oahu that was used as a disposal area for military munitions following World War II. OR has been the subject of multiple investigations including an inventory of munitions conducted by the U.S. Army Corps of Engineers in 2002 and a screening-level risk investigation conducted by the National Oceanic and Atmospheric Administration and the University of Hawaii in 2006. As a result, there are multiple datasets collected over the past fifteen years that can be leveraged to serve as a baseline for the natural laboratory. These extant datasets are being supplemented with data from integrated unmanned systems deployed at OR to characterize and visualize the
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2008 Munitions Executive Summit
2008-02-21
Improvement Initiative • Problem : • Ballistic performance • Parts Obsolescence • Producibility Issues • Solution: • Flight telemetry • Results...Reduced Manufacturing Costs, Increased reliability, Better understanding, Reduced complexity, Reduced touch labor, Reduced material costs • SATISFIED...Rocket Motor Demil R&D Technology •Munitions parts make-up: Munitions Items Disposition Action System ( MIDAS ) Training Directorate •Ammunition
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Optimization of Munitions Storage.
1979-12-01
zones of land around each facility place a significant economic cost on the storage of munitions (Schreyer, 1970: 1). Munitions storage is a subject...ADDTOT, BTOTAL 353 REAL MPH,MW ,MPD, MPU ,4,MPNEW,MCD 354 IF (SW2.NE.0) GO TO 1 355 SW2 - 1 356 WRITE (6,2) 357 GO TO 3 358 1 IF (REC.EQ.0) GO TO 4 359 IF
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Defense Industrial Base (DIB): Munitions Realignment for 2020
2013-03-01
munitions DIB by companies like Coca Cola , Quaker Oats, and Eastman Kodak. As industrial mobilization quickly increased, the requirements decreased...industry and the munitions DIB. This report documented the volatility associated with the production of munitions and financial risks to which
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Observations of Munitions Mobility During a Nor'easter at Wallops Island
Swann, C.; Frank, D. P.; Braithwaite, E. F., III; Hagg, R. K.; Calantoni, J.
2017-12-01
Unexploded ordnance (or munitions) may migrate, bury, or become exposed over time, and may pose a hazard to both humans and environment. Understanding the behavior of munitions under various wave and current conditions is central to management and remediation of contaminated underwater sites. We embedded Inertial Measurement Units (IMUs) into inert replicas of large caliber munitions (81 mm - 155 mm), herein referred to as `smart munitions'. Several smart munitions were deployed in the field with IMUs logging at 16 Hz continuously. Simultaneously the local hydrodynamic conditions were monitored to correlate any resulting munitions mobility. Here, we present the response of the smart munitions to wave and current conditions observed during a nor'easter off the coast of Wallops Island, Virginia USA in about 10 m water depth. During the nor'easter, peak significant wave heights of 2.8 m were observed in 10 m water depth. Over a roughly 10-hour period, an 81 mm smart munition migrated approximately 206 ft in a net onshore direction. Displacement and heading of the migrated smart munition were estimated by divers during the recovery. Integration of the trajectory of motion for the smart munition using a custom signal processing algorithm was in good agreement with the diver measurements. Discussion will focus on the relationship of the local sediment type and the potential for munitions mobility.
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A Wide Area Risk Assessment Framework for Underwater Military Munitions Response
Holland, K. T.; Calantoni, J.
2017-12-01
Our objective was to develop a prototype statistical framework supporting Wide Area Assessment and Remedial Investigation decisions relating to the risk of unexploded ordnance and other military munitions concentrated in underwater environments. Decision making involving underwater munitions is inherently complex due to the high degree of uncertainty in the environmental conditions that force munitions responses (burial, decay, migration, etc.) and associated risks to the public. The prototype framework provides a consistent approach to accurately delineating contaminated areas at underwater munitions sites through the estimation of most probable concentrations. We adapted existing deterministic models and environmental data services for use within statistical modules that allowed the estimation of munition concentration given historic site information and environmental attributes. Ultimately this risk surface can be used to evaluate costs associated with various remediation approaches (e.g. removal, monitoring, etc.). Unfortunately, evaluation of the assessment framework was limited due to the lack of enduser data services from munition site managers. Of the 450 U.S. sites identified as having potential contamination with underwater munitions, assessment of available munitions information (including historic firing or disposal records, and recent ground-truth munitions samples) indicated very limited information in the databases. Example data types include the most probable munition types, approximate firing / disposal dates and locations, and any supportive munition survey or sampling results. However the overall technical goal to integrate trained statistical belief networks with detailed geophysical knowledge of sites, of sensors and of the underwater environment was demonstrated and should allow probabilistic estimates of the most likely outcomes and tradeoffs while managing uncertainty associated with military munitions response.
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Acoustic Scattering from Munitions in the Underwater Environment: Measurements and Modeling
Williams, K.; Kargl, S. G.; Espana, A.
2017-12-01
Acoustical scattering from elastic targets has been a subject of research for several decades. However, the introduction of those targets into the ocean environment brings new complexities to quantitative prediction of that scattering. The goal of our work has been to retain as much of the target physics as possible while also handling the propagation to and from the target in the multi-path ocean environment. Testing of the resulting predictions has been carried out via ocean experiments in which munitions are deployed on and within the sediment. We will present the overall philosophy used in the modeling and then compare model results to measurements. A 60 cm long 30 cd diameter aluminum cylinder will be used as a canonical example and then a sample of results for a variety of munitions will be shown. Finally, we will discuss the use of both the models and measurements in assessing the ability of sonar to discriminate munitions from other man-made targets. The difficulty of this challenge will be made apparent via results from a recent experiment in which both munitions and man-made "clutter" were deployed on a rippled sand interface.
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International Nuclear Information System (INIS)
Haffenden, R.; Kimmell, T.
2002-01-01
This report reviews federal and state hazardous waste regulatory programs that govern the management of chemical weapons or chemical warfare agents. It addresses state programs in the eight states with chemical weapon storage facilities managed by the U.S. Army: Alabama, Arkansas, Colorado, Indiana, Kentucky, Maryland, Oregon, and Utah. It also includes discussions on 32 additional states or jurisdictions with known or suspected chemical weapons or chemical warfare agent presence (e.g., disposal sites containing chemical agent identification sets): Alaska, Arizona, California, Florida, Georgia, Hawaii, Idaho, Illinois, Iowa, Kansas, Louisiana, Massachusetts, Michigan, Mississippi, Missouri, Nebraska, Nevada, New Jersey, New Mexico, New York, North Carolina, Ohio, Pennsylvania, South Carolina, South Dakota, Tennessee, Texas, the U.S. Virgin Islands, Virginia, Washington, Washington, D.C., and Wyoming. Resource Conservation and Recovery Act (RCRA) hazardous waste programs are reviewed to determine whether chemical weapons or chemical warfare agents are listed hazardous wastes or otherwise defined or identified as hazardous wastes. Because the U.S. Environmental Protection Agency (EPA) military munitions rule specifically addresses the management of chemical munitions, this report also indicates whether a state has adopted the rule and whether the resulting state regulations have been authorized by EPA. Many states have adopted parts or all of the EPA munitions rule but have not yet received authorization from EPA to implement the rule. In these cases, the states may enforce the adopted munitions rule provisions under state law, but these provisions are not federally enforceable
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Chemical Munitions Dumped at Sea near the Hawaiian Islands
Edwards, M.; Bissonnette, M. C.; Briggs, C. W.; Shjegstad, S. M.
2016-12-01
Sea disposal was once internationally accepted as an appropriate method for disposal of excess, obsolete, and unserviceable conventional and chemical munitions. The past decade has seen an increase in the number and complexity of studies to assess the effects of historical munitions disposal in the oceans. The Hawai`i Undersea Military Munitions Assessment (HUMMA) is a comprehensive deep-water (300-600 meter) investigation designed to determine the potential impact of sea-disposed munitions on the ocean environment, and vice versa, at a disposal site south of Pearl Harbor, Oahu, Hawaii. Historical records indicated that as many as 16,000 mustard-filled bombs were disposed in this area following World War II. A secondary objective of HUMMA is to determine best practices and technologies for mapping and sampling sea-disposed munitions. The overarching result from five HUMMA field programs conducted over a decade is that the greatest risk from munitions derives from direct contact; there is little evidence that leakage from munitions into the surrounding environment has a direct pathway to affect human health and the impact on the surrounding environment in Hawaii is detectable only at trace levels. This finding should be modulated based on the quantity of physical samples, which were collected around detected at control sites. Both findings support a hypothesis that the impacts of sea-disposed munitions change over time. This presentation will describe the technical approach and results of the 2014 HUMMA field program using Jason 2.
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19 CFR 145.53 - Firearms and munitions of war.
2010-04-01
... 19 Customs Duties 2 2010-04-01 2010-04-01 false Firearms and munitions of war. 145.53 Section 145.53 Customs Duties U.S. CUSTOMS AND BORDER PROTECTION, DEPARTMENT OF HOMELAND SECURITY; DEPARTMENT OF... munitions of war. Importations of firearms, munitions of war, and related articles are subject to the import...
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Federal Laboratory Consortium — Insensitive Munitions Testing at RTC is conducted (IAW MILSTD-2105) at Test Area 4. Our engineers and technicians obtain data for hazards classification and safety...
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Sea-dumped CW munitions - the European component
International Nuclear Information System (INIS)
Hart, J.; Stock, T.
2009-01-01
The purpose of this contribution is to outline the European magnitude of sea-dumped CW munitions. Hereby the paper attempts to provide an overview on historical dumping activities, both for conventional and chemical munitions. The potential dangers which might result from these dumping activities are discussed in brief. Among others the differences in deep sea dumping and dumping in shallow waters are evaluated. Further, the presentation will outline and discuss the different technology steps: (a) identification, (b) recovery, (c) transportation and (d) destruction (on- or off-shore), necessary for possible cleaning of dumping sites. Thereafter an evaluation of the different technologies available/applied is performed, in particular on the destruction part. Hereby the already practised experience is displayed. Based upon existing treaty regimes an actual judgment of possible application of treaty provisions for demanding cleaning up operations is discussed. The question if treaty obligations can be used to force cleaning operations is debated. A possible match of the technology package available with the scope/magnitude of the munitions dumping problem is discussed. Hereby the gaps between the size of the problem and the most suitable technologies for recovery and destruction are illustrated. The resulting answers should be regarded as possible technical guidelines for future development activities as well existing limitations to solve the problems. The papers will result in some general guidelines for future prospect on the issues of dumped munitions, in particular chemical munitions under the European context.(author)
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Innovative permeable cover system to reduce risks at a chemical munitions burial site
International Nuclear Information System (INIS)
Powels, C.C.; Bon, I.; Okusu, N.M.
1997-01-01
An innovative permeable sand cover with various integrated systems has been designed to contain and treat the Old O-Field chemical munitions landfill at Aberdeen Proving Ground, Maryland. The 18,200 m 2 (4.5 acre) landfill was used from the mid 1930s to the mid 1950s for the disposal of chemical, incendiary, and explosive munitions from domestic and foreign origins, together with contaminated wastes associated with the development and production of chemical warfare agents (CWA). The site is suspected to be contaminated with white phosphorous (WP) (which when dry, spontaneously burns when exposed to air), shock sensitive picric acid fuses and has the potential to contain large quantities of CWA-filled munitions. Historically, one to three explosions or fires occurred per ten-year period at the landfill. Such events have the potential to cause a CWA release to the environment, which could potentially affect densely populated areas. Recovery and decontamination projects conducted at the site in the late 1940s and early 1950s used large amounts of decontamination chemicals (containing solvents) and fuels which further contaminated the area. The groundwater downgradient of the landfill is contaminated with volatile organic compounds, metals, explosives and CWA degradation compounds and is currently being contained by a groundwater extraction and treatment system. This report describes a remedial action program for the site
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Missile/Munition Integration Facility
Federal Laboratory Consortium — A large complex contained within approximately 600 acres with security fencing, controlled access gates, and a munitions convoy access road. The complex is capable...
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The Environmental Challenge of Military Munitions and Federal Facilities
EPA and the Department of Defense (DoD) must address the contamination legacy left by military munitions and explosives of concern (MEC) and other hazardous munitions materials from military live-fire training or testing.
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Munitions Classification Library
2016-04-04
members of the community to make their own additions to any, or all, of the classification libraries . The next phase entailed data collection over less......Include area code) 04/04/2016 Final Report August 2014 - August 2015 MUNITIONS CLASSIFICATION LIBRARY Mr. Craig Murray, Parsons Dr. Thomas H. Bell, Leidos
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Optimal Control of Sensor Threshold for Autonomous Wide Area Search Munitions
National Research Council Canada - National Science Library
Kish, Brian A; Jacques, David R; Pachter, Meir
2005-01-01
The optimal employment of autonomous wide area search munitions is addressed. The scenario considered involves an airborne munition searching a battle space for stationary targets in the presence of false targets...
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Munitions in the Underwater Environment: State of the Science and Knowledge Gaps
2010-06-01
the Munitions Items Disposition Action System ( MIDAS ). Munitions constituents (MCs) can be identified through the known munitions type. The MIDAS and...physical damage to the casing, adjacent or touching metals, and water or substrate qualities such as temperature, pH, or Redox potential. The...environments, little is known on modeling the fate of MCs in the underwater environment. One of the anticipated problems in predicting the fate and
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2017-09-01
TNT TOC TSS Low Order Detonation Munitions constituents Munitions Debris Method Detection Limit Munitions and explosives of concern Mean low...Total organic carbon ( TOC ) and grain size distribution from stations A1, T10, T11, and T12 at BSS...16 syringes/stn) TNT, ADNTs, DNTs, RDX 4 locations in BSS based on positive POCIS results Sediment 5 TOC , grain size 4, co-located with sediment
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Eksplozivne materije za neosetljiva ubojna sredstva / Explosive substances for insensitive munitions
Directory of Open Access Journals (Sweden)
Radun Jeremić
2005-03-01
Full Text Available U skladu sa sve strožim zahtevima za očuvanje životne sredine i većom bezbednošću, tendencije u razvoju suvremenih ubojnih sredstava (UbS, pored povećanja pouzdanosti i efikasnosti, usmerene su i na povećanje sigurnosti pri njihovoj proizvodnji, skladištenju, manipulaciji i upotrebi. Na taj način dobijena je nova kategorija UbS, tzv. neosetljiva UbS, kod kojih je verovatnoća neželjenog aktiviranja pod dejstvom spoljnih impulsa svedena na minimum. Suština rešavanja ovog problema je primena eksplozivnih materija koje su mnogo manje osetljive na spoljne uticaje u odnosu na standardne. Osnovni zahtev koji se pri tome postavlja je da taktičko-tehničke karakteristike ostanu na nivou ili budu bolje u odnosu na postojeća UbS. U radu je ukratko objašnjen koncept razvoja neosetljivih UbS i dat pregled najznačajnijih rezultata istraživanja u oblasti eksplozivnih materija koje zadovoljavaju zahteve za primenu u neosetljivim UbS. / According to severe environment protection and safety requirements, tendencies in development of modern munitions, besides of increasing reliability and efficiency, are directed to decreasing of danger during their processing, storing, handling and operating. In that manner the new category of munitions has been obtained, named insensitive munitions, with a minimum probability of unplanned activating. The best method for solving this problem is using of explosive substances that are more insensitive according to standard ones. The main requirement is the tactical and technical characteristics stay at the level or to be better according to the existing munitions. In this paper the developing concept of insensitive munitions is shortly explained and presented a review of most important research results of explosive materials that fulfill requirements for applying in insensitive munitions.
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Gilooly, S.; Foster, D. L.
2017-12-01
In nearshore environments, the motion of munitions results from a mixture of sediment transport conditions including sheet flow, scour, bedform migration, and momentary liquefaction. Incipient motion can be caused by disruptive shear stresses and pressure gradients. Foster et al. (2006) incorporated both processes into a single parameter, indicating incipient motion as a function of the bed state. This research looks to evaluate the role of the pressure gradient in positional state changes such as burial, exposure, and mobility. In the case of munitions, this may include pressure gradients induced by vortex shedding or the passing wave. Pressure-mapped model munitions are being developed to measure the orientation, rotation, and surface pressure of the munitions during threshold events leading to a new positional state. These munitions will be deployed in inner surf zone and estuary environments along with acoustic Doppler velocimeters (ADVs), pore water pressure sensors, a laser grid, and a pencil beam sonar with an azimuth drive. The additional instruments allow for near bed and far field water column and sediment bed sampling. Currently preliminary assessments of various pressure sensors and munition designs are underway. Two pressure sensors were selected; the thin FlexiForce A201 sensors will be used to indicate munition rolling during threshold events and diaphragm sensors will be used to understand changes in surrounding pore water pressure as the munition begins to bury/unbury. Both sensors are expected to give quantitative measurements of dynamic pressure gradients in the flow field surrounding the munition. Resolving the role of this process will give insight to an improved incipient motion parameter and allow for better munition motion predictions.
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2018-04-26
2018 IM & EM TECHNOLOGY SYMPOSIUM INNOVATIVE INSENSITIVE MUNITION SOLUTIONS FOR ENHANCED WARFIGHTER EFFECTIVENESS April 23 – 26, 2018 Doubletree by...IM & EM TECHNOLOGY SYMPOSIUM On behalf of the Insensitive Munitions and Energetic Materials Committee and our MSIAC partner, I would like to...welcome you to the 2018 Insensitive Munitions and Energetic Materials Technology Symposium. This international gathering of the top chemists, system
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Cluster munitions: public health and international humanitarian law perspectives.
Freckelton, Ian
2008-02-01
As a result of civilian deaths in Vietnam, Cambodia, Laos, Chechnya, Kosovo, Afghanistan, Iraq and Lebanon, cluster munitions have been recognised to pose a grave threat to civilian populations because of their limited precision and problematically high rate of initial failure to explode. Efforts are intensifying to ban cluster munitions and to mandate those who have discharged them to defuse them effectively so as to reduce the risks to civilians. This editorial reviews these efforts and identifies a need for them to be actively supported by both the legal and medical communities.
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Observation of Burial and Migration of Instrumented Surrogate Munitions Deployed in the Swash Zone
Cristaudo, D.; Puleo, J. A.; Bruder, B. L.
2017-12-01
Munitions (also known as unexploded ordnance; UXO) in the nearshore environment due to past military activities, may be found on the beach, constituting a risk for beach users. Munitions may be transported from offshore to shallower water and/or migrate along the coast. In addition, munitions may bury in place or be exhumed due to hydrodynamic forcing. Observations on munitions mobility have generally been collected offshore, while observations in the swash zone are scarce. The swash zone is the region of the beach alternately covered by wave runup where hydrodynamic processes may be intense. Studies of munitions mobility require the use of realistic surrogates to quantify mobility/burial and hydrodynamic forcing conditions. Four surrogates (BLU-61 Cluster Bomb, 81 mm Mortar, M151-70 Hydra Rocket and M107 155 mm High Explosive Howitzer) were developed and tested during large-scale laboratory and field studies. Surrogates house sensors that measure different components of motion. Errors between real munitions and surrogate parameters (mass, center of gravity and axial moment of inertia) are all within an absolute error of 20%. Internal munitions sensors consist of inertial motion units (for acceleration and angular velocity in and around the three directions and orientation), pressure transducers (for water depth above surrogate), shock recorders (for high frequency acceleration to detect wave impact on the surrogate), and an in-house designed array of optical sensors (for burial/exposure and rolling). An in situ array of sensors to measure hydrodynamics, bed morphology and sediment concentrations, was deployed in the swash zone, aligned with the surrogate deployment. Data collected during the studies will be shown highlighting surrogate sensor capabilities. Sensors response will be compared with GPS measurements and imagery from cameras overlooking the study sites of surrogate position as a function of time. Examples of burial/exposure and migration of surrogates
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Trauma-related infections due to cluster munitions.
Fares, Youssef; El-Zaatari, Mohamad; Fares, Jawad; Bedrosian, Nora; Yared, Nadine
2013-12-01
Trauma-related infections remain a concerning and potentially avoidable complication of conflict-related injuries. During the Israeli conflict in South Lebanon, more than four million sub-munitions were dropped over South Lebanese soil. In this study, we will explore the different types of infection caused by sub-munitions and penetrating agents. This prospective study took place from 2006 to 2012 at the Lebanese University within the Faculty of Medical Sciences' departments. This study sample consisted of 350 injured casualties. Patients suffered from blast injuries with fragmentations targeting the head, face, torso, abdomen, pelvis and extremities. Of the 350 causalities studied, 326 (93.1%) were males, and 24 (6.9%) were females. Ages varied between 10 and 70 years, with the average age being 27 years. Of the 350 patients studied, 68 (19.4%) developed infections. Infections varied between pseudomonas, Escherichia coli, Candida and fungus and sometimes led to necrosis. Vaccinations, antibiotic therapies and proper wound irrigation must be performed at appropriate emergency units. Excision and complete debridement of necrotic and contaminated tissue should also be performed. The Convention on Cluster Munitions of 2008 should be adhered to, as these weapons indiscriminately and disproportionately harm civilians, thereby violating the well-established international principles governing conflict. Copyright © 2013 King Saud Bin Abdulaziz University for Health Sciences. Published by Elsevier Ltd. All rights reserved.
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28 CFR 0.89 - Authority to seize arms and munitions of war.
2010-07-01
... war. 0.89 Section 0.89 Judicial Administration DEPARTMENT OF JUSTICE ORGANIZATION OF THE DEPARTMENT OF JUSTICE Federal Bureau of Investigation § 0.89 Authority to seize arms and munitions of war. The Director... arms and munitions of war, and other articles, pursuant to section 1 of title VI of the act of June 15...
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Optimal path planning for video-guided smart munitions via multitarget tracking
Borkowski, Jeffrey M.; Vasquez, Juan R.
2006-05-01
An advent in the development of smart munitions entails autonomously modifying target selection during flight in order to maximize the value of the target being destroyed. A unique guidance law can be constructed that exploits both attribute and kinematic data obtained from an onboard video sensor. An optimal path planning algorithm has been developed with the goals of obstacle avoidance and maximizing the value of the target impacted by the munition. Target identification and classification provides a basis for target value which is used in conjunction with multi-target tracks to determine an optimal waypoint for the munition. A dynamically feasible trajectory is computed to provide constraints on the waypoint selection. Results demonstrate the ability of the autonomous system to avoid moving obstacles and revise target selection in flight.
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Mixed Waste Working Group report
International Nuclear Information System (INIS)
1993-01-01
The treatment of mixed waste remains one of this country's most vexing environmental problems. Mixed waste is the combination of radioactive waste and hazardous waste, as defined by the Resource Conservation and Recovery Act (RCRA). The Department of Energy (DOE), as the country's largest mixed waste generator, responsible for 95 percent of the Nation's mixed waste volume, is now required to address a strict set of milestones under the Federal Facility Compliance Act of 1992. DOE's earlier failure to adequately address the storage and treatment issues associated with mixed waste has led to a significant backlog of temporarily stored waste, significant quantities of buried waste, limited permanent disposal options, and inadequate treatment solutions. Between May and November of 1993, the Mixed Waste Working Group brought together stakeholders from around the Nation. Scientists, citizens, entrepreneurs, and bureaucrats convened in a series of forums to chart a course for accelerated testing of innovative mixed waste technologies. For the first time, a wide range of stakeholders were asked to examine new technologies that, if given the chance to be tested and evaluated, offer the prospect for better, safer, cheaper, and faster solutions to the mixed waste problem. In a matter of months, the Working Group has managed to bridge a gap between science and perception, engineer and citizen, and has developed a shared program for testing new technologies
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Chemical Warfare Materiel in Sediment at a Deep-Water Discarded Military Munitions Site
Briggs, C. W.; Bissonnette, M. C.; Edwards, M.; Shjegstad, S. M.
2016-12-01
Understanding the release and transformation of chemical agent (CA) at underwater discarded military munitions (DMM) sites is essential to determine the potential risk to human health and impact on the ocean environment; yet few studies have been conducted at sites in excess of 250 m, the depth at which most U.S. CA munitions were disposed. Maritime construction workers installing cables or pipelines at a CA DMM site, as well as fishermen and scientific researchers deploying bottom-contact gear, represent possible exposure pathways to human receptors. The Hawai`i Undersea Military Munitions Assessment (HUMMA) sought to characterize a historic munitions sea-disposal site at depths between 400-650 m. During the 2014 HUMMA Sampling Survey, the Jason 2 remotely operated vehicle was used to collect sediments within two meters of suspected World War II chemical munitions, confirmed to be 100-lb M47 series bombs containing sulfur mustard. When environmental media was brought to the surface, samples were screened for distilled sulfur mustard (HD) and related agent breakdown products (ABP) (collectively referred to as chemical warfare materiel [CWM]). Detectable concentrations of HD and/or its ABP 1,4-dithiane were found in sediments collected at all CA DMM sites; HD was also detected at two control sites. The location and extent of munitions casing deterioration strongly influenced the distribution and level of CWM in sediment. The interior of the casing contained levels of CWM orders of magnitudes higher than that observed in the surrounding sediment at one meter distance, indicating the majority of the CWM is hydrolyzed as it is released from the munitions casing and a fraction of the fill materiel persists in the environment for decades following disposal. Although the potential for future site users to become exposed to CWA in recovered sediments and debris exists, the level of risk is significantly mitigated by the depth and location of the sea-disposal site.
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Abandoned Mine Waste Working Group report
International Nuclear Information System (INIS)
1993-01-01
The Mine Waste Working Group discussed the nature and possible contributions to the solution of this class of waste problem at length. There was a consensus that the mine waste problem presented some fundamental differences from the other classes of waste addresses by the Develop On-Site Innovative Technologies (DOIT) working groups. Contents of this report are: executive summary; stakeholders address the problems; the mine waste program; current technology development programs; problems and issues that need to be addressed; demonstration projects to test solutions; conclusion-next steps; and appendices
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High-power VCSELs for smart munitions
Geske, Jon; MacDougal, Michael; Cole, Garrett; Snyder, Donald
2006-08-01
The next generation of low-cost smart munitions will be capable of autonomously detecting and identifying targets aided partly by the ability to image targets with compact and robust scanning rangefinder and LADAR capabilities. These imaging systems will utilize arrays of high performance, low-cost semiconductor diode lasers capable of achieving high peak powers in pulses ranging from 5 to 25 nanoseconds in duration. Aerius Photonics is developing high-power Vertical-Cavity Surface-Emitting Lasers (VCSELs) to meet the needs of these smart munitions applications. The authors will report the results of Aerius' development program in which peak pulsed powers exceeding 60 Watts were demonstrated from single VCSEL emitters. These compact packaged emitters achieved pulse energies in excess of 1.5 micro-joules with multi kilo-hertz pulse repetition frequencies. The progress of the ongoing effort toward extending this performance to arrays of VCSEL emitters and toward further improving laser slope efficiency will be reported.
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Remote Machining and Evaluation of Explosively Filled Munitions
Federal Laboratory Consortium — This facility is used for remote machining of explosively loaded ammunition. Munition sizes from small arms through 8-inch artillery can be accommodated. Sectioning,...
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2017-06-30
Research and Development Program [SERDP] project #ER-2542) into the canister would provide enhancement of the quantitative estimation of the TWA...Department of Defense EOD Explosive Ordnance Disposal EPA United States Environmental Protection Agency EQL Environmental Quantitation Limit EST...Laboratory Quantitation Limit MC Munitions Constituents mL Milliliter MR Munitions Response NESDI Navy’s Environmental Security Development to
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Munition Burial by Local Scour and Sandwaves: large-scale laboratory experiments
Garcia, M. H.
2017-12-01
Our effort has been the direct observation and monitoring of the burial process of munitions induced by the combined action of waves, currents and pure oscillatory flows. The experimental conditions have made it possible to observe the burial process due to both local scour around model munitions as well as the passage of sandwaves. One experimental facility is the Large Oscillating Water Sediment Tunnel (LOWST) constructed with DURIP support. LOWST can reproduce field-like conditions near the sea bed. The second facility is a multipurpose wave-current flume which is 4 feet (1.20 m) deep, 6 feet (1.8 m) wide, and 161 feet (49.2 m) long. More than two hundred experiments were carried out in the wave-current flume. The main task completed within this effort has been the characterization of the burial process induced by local scour as well in the presence of dynamic sandwaves with superimposed ripples. It is found that the burial of a finite-length model munition (cylinder) is determined by local scour around the cylinder and by a more global process associated with the formation and evolution of sandwaves having superimposed ripples on them. Depending on the ratio of the amplitude of these features and the body's diameter (D), a model munition can progressively get partially or totally buried as such bedforms migrate. Analysis of the experimental data indicates that existing semi-empirical formulae for prediction of equilibrium-burial-depth, geometry of the scour hole around a cylinder, and time-scales developed for pipelines are not suitable for the case of a cylinder of finite length. Relative burial depth (Bd / D) is found to be mainly a function of two parameters. One is the Keulegan-Carpenter number, KC, and the Shields parameter, θ. Munition burial under either waves or combined flow, is influenced by two different processes. One is related to the local scour around the object, which takes place within the first few hundred minutes of flow action (i.e. short
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U.S. Army Training and Testing Area Carrying Capacity (ATTACC) for Munitions (AFM)
2006-11-01
Army Training Support Center USDA United States Department of Agriculture USGS United States Geological Survey USLE Universal Soil Loss Equation...Range condition is a function of climate, soil , and hydrology. The munitions impact, constituent load, and range condition are modeled using AFM...For ArcGIS v2 to attain expected concentrations of munitions constituents and corresponding risk due to exposure through soil - and water-related
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Energy Technology Data Exchange (ETDEWEB)
Chester, C.V.
1990-08-01
A brief study was made of some of the forces driving the move to Precision Guided Munitions (PGMs), including the quest for military effectiveness, combat experience, and logistic compression. PGMs cost from a few hundred to a few thousand dollars per Kg but are tens to hundreds of times more effective than conventional munitions. A year's peacetime plateau production of each US PGM can be carried by a few C-5 aircraft. Surge quantities of PGMs are within US airlift capabilities, taking some of the risk out of off-shore procurement. The improving capability of antiaircraft PGMs and the escalating cost of combat aircraft (50 to 100-fold in constant dollars since WW II) may bring into question the economic viability of manned attack aircraft. The same may be true to a slightly lesser degree for heavy armored vehicles. 14 refs., 5 tabs.
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Service life determination of munition during expeditionary missions
Klerk, W.P.C. de; Heijden, A.E.D.M. van der
2012-01-01
For a more in-depth understanding of the aging processes of munitions in expeditionary operations, research is performed with respect to the influence of transport, storage and use on the safety of ammunition. Within this programme the influences of parameters like temperature, humidity, vibrations,
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Briggs, Christian; Shjegstad, Sonia M.; Silva, Jeff A. K.; Edwards, Margo H.
2016-06-01
There is a strong need to understand the behavior of chemical warfare agent (CWA) at underwater discarded military munitions (DMM) sites to determine the potential threat to human health or the environment, yet few studies have been conducted at sites in excess of 250 m, the depth at which most U.S. chemical munitions were disposed. As part of the Hawai'i Undersea Military Munitions Assessment (HUMMA), sediments adjacent to chemical and conventional DMM at depths of 400-650 m were sampled using human occupied vehicles (HOVs) in order to quantify the distribution of CWA, energetics, and select metals. Sites in the same general area, with no munitions within 50 m in any direction were sampled as a control. Sulfur mustard (HD) and its degradation product 1,4-dithiane were detected at each CWA DMM site, as well as a single sample with the HD degradation product 1,4-thioxane. An energetic compound was detected in sediment to a limited extent at one CWA DMM site. Metals common in munitions casings (i.e., Fe, Cu, and Pb) showed similar trends at the regional and site-wide scales, likely reflecting changes in marine sediment deposition and composition. This study shows HD and its degradation products can persist in the deep-marine environment for decades following munitions disposal.
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Energy Technology Data Exchange (ETDEWEB)
Desailly, D.; Briquet, B.; Brunet, P.; Guegant, Y.; Houdusse, D.; Prost, M. [Groupe SNPE Propulsion/ Centre de Recherches du Boucher, 91 - Vert le Petit (France)
2002-09-01
Vulnerability of new weapon systems to accidental and hostile environments is a major concern for military operations and many research programs have been so investigated of SNPE Propulsion. Before they were accepted as being safe and suitable for introduction into military inventories systems underwent a wide range of expensive type qualification trials. There was a need therefore, to develop a greater understanding of the reaction mechanisms that affect the behaviour of confined energetic materials when subjected to external stimuli and computer models to control the resulting hazard. As part of this program SNPE Propulsion has developed a method for modelling Cook-off response in order to master the design of insensitive munitions (IM). The behavior of energetic materials when they are submitted to a thermal threat is complex and follows two different time scales: thermochemical processes, counted in minutes even hours whereas pyrotechnic reaction may require a few microseconds. It was shown that the reaction level is ruled by the competition between pressure generated from the cook-off reaction and stress release resulting from break-up confinement. After self-ignition phenomenon and under some confinement and thermal conditions burning can accelerate to deflagration and lead to a deflagration to detonation transition (DDT) event. The method requires'modular tools describing each physical phenomenon. Works have been first focused on the development of experimental facilities to characterise thermal chemical properties and reactivity of thermally damaged energetic material. Consequently the first part of the model describing self-heating and pyrolysis processes has been implemented in an implicit solver. Simulations have shown quite accurate predictions (ignition temperature, time to event) and proved the effectiveness of this approach. Recent developments are.thus concentrated on the numerical modelling of the reaction violence level prediction hence a
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Koide, Shelby; Silva, Jeff A. K.; Dupra, Vilma; Edwards, Margo
2016-06-01
The bioaccumulation of munitions-related chemicals at former military deep-water disposal sites is poorly understood. This paper presents the results of human-food-item biota sampling to assess the potential for bioaccumulation of chemical warfare agents, energetic materials, arsenic, and additional munitions-related metals in deep-sea shrimp tissue samples collected during the Hawai'i Undersea Military Munitions Assessment (HUMMA) project to date. The HUMMA investigation area is located within a former munitions sea-disposal site located south of Pearl Harbor on the island of O'ahu, Hawai'i, designated site Hawaii-05 (HI-05) by the United States Department of Defense. Indigenous deep-sea shrimp (Heterocarpus ensifer) were caught adjacent to discarded military munitions (DMM) and at control sites where munitions were absent. Tissue analysis results showed that chemical warfare agents and their degradation products were not present within the edible portions of these samples at detectable concentrations, and energetic materials and their degradation products were detected in only a few samples at concentrations below the laboratory reporting limits. Likewise, arsenic, copper, and lead concentrations were below the United States Food and Drug Administration's permitted concentrations of metals in marine biota tissue (if defined), and their presence within these samples could not be attributed to the presence of DMM within the study area based on a comparative analysis of munitions-adjacent and control samples collected. Based on this current dataset, it can be concluded that DMM existing within the HUMMA study area is not contributing to the bioaccumulation of munitions-related chemicals for the biota species investigated to date.
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2010-10-01
... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Prohibition on acquisition of United States Munitions List items from Communist Chinese military companies. 225.770 Section 225... of United States Munitions List items from Communist Chinese military companies. This section...
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A two-stage extraction procedure for insensitive munition (IM) explosive compounds in soils.
Felt, Deborah; Gurtowski, Luke; Nestler, Catherine C; Johnson, Jared; Larson, Steven
2016-12-01
The Department of Defense (DoD) is developing a new category of insensitive munitions (IMs) that are more resistant to detonation or promulgation from external stimuli than traditional munition formulations. The new explosive constituent compounds are 2,4-dinitroanisole (DNAN), nitroguanidine (NQ), and nitrotriazolone (NTO). The production and use of IM formulations may result in interaction of IM component compounds with soil. The chemical properties of these IM compounds present unique challenges for extraction from environmental matrices such as soil. A two-stage extraction procedure was developed and tested using several soil types amended with known concentrations of IM compounds. This procedure incorporates both an acidified phase and an organic phase to account for the chemical properties of the IM compounds. The method detection limits (MDLs) for all IM compounds in all soil types were regulatory risk-based Regional Screening Level (RSL) criteria for soil proposed by the U.S. Army Public Health Center. At defined environmentally relevant concentrations, the average recovery of each IM compound in each soil type was consistent and greater than 85%. The two-stage extraction method decreased the influence of soil composition on IM compound recovery. UV analysis of NTO established an isosbestic point based on varied pH at a detection wavelength of 341 nm. The two-stage soil extraction method is equally effective for traditional munition compounds, a potentially important point when examining soils exposed to both traditional and insensitive munitions. Copyright © 2016 Elsevier Ltd. All rights reserved.
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20000G shock energy harvesters for gun-fired munition
International Nuclear Information System (INIS)
Willemin, J.; Boisseau, S.; Olmos, L.; Gallardo, M.; Despesse, G.; Robert, T.
2016-01-01
This paper presents a 20000G shock energy harvester dedicated to gun-fired munitions and based on a mass-spring resonant structure coupled to a coil-magnet electromagnetic converter. The 20000G shock energy is firstly stored in the spring as elastic potential energy, released as mass-spring mechanical oscillations right after the shock and finally converted into electricity thanks to the coil-magnet transducer. The device has been modeled, sized to generate 200mJ in 150ms, manufactured and tested in a gun-fired munition. The prototype sizes 117cm 3 and weighs 370g. 210mJ have been generated in a test bench and 140mJ in real conditions; this corresponds to a mean output power of 0.93W (7.9mW/cm 3 ) and a maximum output power of 4.83W (41.3mW/cm 3 ) right after the shock. (paper)
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20000G shock energy harvesters for gun-fired munition
Willemin, J.; Boisseau, S.; Olmos, L.; Gallardo, M.; Despesse, G.; Robert, T.
2016-11-01
This paper presents a 20000G shock energy harvester dedicated to gun-fired munitions and based on a mass-spring resonant structure coupled to a coil-magnet electromagnetic converter. The 20000G shock energy is firstly stored in the spring as elastic potential energy, released as mass-spring mechanical oscillations right after the shock and finally converted into electricity thanks to the coil-magnet transducer. The device has been modeled, sized to generate 200mJ in 150ms, manufactured and tested in a gun-fired munition. The prototype sizes 117cm3 and weighs 370g. 210mJ have been generated in a test bench and 140mJ in real conditions; this corresponds to a mean output power of 0.93W (7.9mW/cm3) and a maximum output power of 4.83W (41.3mW/cm3) right after the shock.
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2010-10-01
... of United States Munitions List Items from Communist Chinese Military Companies. 252.225-7007 Section... Chinese Military Companies. As prescribed in 225.1103(4), use the following clause: Prohibition On Acquisition of United States Munitions List Items From Communist Chinese Military Companies (SEP 2006) (a...
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Health and environmental problems of using antiarmour munitions containing depleted uranium core
International Nuclear Information System (INIS)
Matousek, J.
2006-01-01
In the 1970s, core of depleted uranium commenced to be introduced into the breakthrough antitank munitions of various calibers and types in order to considerably enhance their effectiveness due to extremely high density in comparison with steel. The health and environmental threats of using this munitions and other weaponry where depleted uranium has been utilised as counterbalance stem from the pyrophoric character of uranium, burnt due to material deformation and friction when penetrating armour targets creating thus highly respirable aerosol of uranium oxides that are deposited in alveoli after being inhaled or in other tissues after being ingested. Composition and main properties of depleted uranium are presented. Chronic effects of deposited particles of uranium oxides are due to internal irradiation of sensitive organs at proceeding radioactive decay accompanied with alpha irradiation. Long-term internal irradiation by radionuclides producing alpha-rays leads to proved risk of increased incidence of carcinoma and leukaemia not to speak on chronic chemical toxicity of uranium, independent of its isotopic composition. Environmental impact of extensive use of munitions with depleted uranium in the recent armed conflicts is assessed. (authors)
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In-Flight Self-Alignment Method Aided by Geomagnetism for Moving Basement of Guided Munitions
Directory of Open Access Journals (Sweden)
Shuang-biao Zhang
2015-01-01
Full Text Available Due to power-after-launch mode of guided munitions of high rolling speed, initial attitude of munitions cannot be determined accurately, and this makes it difficult for navigation and control system to work effectively and validly. An in-flight self-alignment method aided by geomagnetism that includes a fast in-flight coarse alignment method and an in-flight alignment model based on Kalman theory is proposed in this paper. Firstly a fast in-flight coarse alignment method is developed by using gyros, magnetic sensors, and trajectory angles. Then, an in-flight alignment model is derived by investigation of the measurement errors and attitude errors, which regards attitude errors as state variables and geomagnetic components in navigation frame as observed variables. Finally, fight data of a spinning projectile is used to verify the performance of the in-flight self-alignment method. The satisfying results show that (1 the precision of coarse alignment can attain below 5°; (2 the attitude errors by in-flight alignment model converge to 24′ at early of the latter half of the flight; (3 the in-flight alignment model based on Kalman theory has better adaptability, and show satisfying performance.
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Disposal of chemical agents and munitions stored at Pine Bluff Arsenal, Pine Bluff, Arkansas
Energy Technology Data Exchange (ETDEWEB)
Ensminger, J.T.; Hillsman, E.L.; Johnson, R.D.; Morrisey, J.A.; Staub, W.P.; Boston, C.R.; Hunsaker, D.B.; Leibsch, E.; Rickert, L.W.; Tolbert, V.R.; Zimmerman, G.P.
1991-09-01
The Pine Bluff Arsenal (PBA) near Pine Bluff, Arkansas, is one of eight continental United States (CONUS) Army installations where lethal unitary chemical agents and munitions are stored and where destruction of agents and munitions is proposed under the Chemical Stockpile Disposal Program (CSDP). The chemical agent inventory at PBA consists of approximately 12%, by weight, of the total US stockpile. The destruction of the stockpile is necessary to eliminate the risk to the public from continued storage and to dispose of obsolete and leaking munitions. In 1988 the US Army issued a Final Programmatic Environmental Impact Statement (FPEIS) for the CSDP that identified on-site disposal of agents and munitions as the environmentally preferred alternative (i.e., the alternative with the least potential to cause significant adverse impacts). The purpose of this report is to examine the proposed implementation of on-site disposal at PBA in light of more recent and more detailed data than those on which the FPEIS is based. New population data were used to compute fatalities using the same computation methods and values for all other parameters as in the FPEIS. Results indicate that all alternatives are indistinguishable when the potential health impacts to the PBA community are considered. However, risks from on-site disposal are in all cases equal to or less than risks from other alternatives. Furthermore, no unique resources with the potential to prevent or delay implementation of on-site disposal at PBA have been identified.
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Management of radioactive wastes arising from the use of Australian radioisotopes
International Nuclear Information System (INIS)
Costello, J.M.
1986-01-01
The medical, industrial and research use of radioisotopes in Australia has given rise to approximately 30 m 3 of solid radioactive waste containing about 5 TBq of radioactivity. This waste is stored at State hospitals, universities and research centres. A further 10 m 3 of waste containing 300 GBq of radioactivity is stored by the Commonwealth at the St Mary's Munitions Filling factory. About 700 m 3 of waste containing 1.5 PBq of radioactivity resulting from operation of the HIFAR nuclear reactor and the production of radioisotopes is in storage at the Lucas Heights Research Establishment. The source, nature and rate of arising of these wastes is reviewed, together with national developments in waste classification, storage procedures and eventual disposal. Some research at Lucas Heights on the conditioning of radioisotope waste to facilitate disposal is briefly noted
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Warren, Joseph K; Vlahos, Penny; Smith, Richard; Tobias, Craig
2018-07-01
Over the last century, unexploded ordnances have been disposed of in marine shelf systems because of a lack of cost-effective alternatives. Underwater unexploded ordnances have the potential to leak 2,4,6-trinitrotoluene (TNT) and 1,3,5-trinitro-1,3,5-triazine (RDX), commonly used chemical munitions, and contaminate local waters, biota, and sediments. The rate at which this contamination occurs in the environment is relatively unknown, and the cost- and time-prohibitive nature of sampling across sites makes mapping difficult. In the present study we assessed the efficacy of ethylene-vinyl acetate (EVA) for sampling relatively soluble munitions compounds over a range of environmental conditions (i.e., changes in temperature and salinity) and optimized the composition of the passive sampling polymer. The EVA sampler was able to successfully detect ambient concentrations of lingering munitions compounds from field sites containing unexploded ordnances. The sampler affinity for the munitions in terms of an EVA-water partition coefficient was greater than the standard octanol water values for each target compound. Partitioning of compounds onto EVA over the natural ranges of salinity did not change significantly, although uptake varied consistently and predictably with temperature. Increasing the vinyl acetate to ethylene ratio of the polymer corresponded to an increase in uptake capacity, consistent with enhanced dipole-dipole interactions between the munitions and the polymer. This sampler provides a cost-effective means to map and track leakage of unexploded ordnances both spatially and temporally. Environ Toxicol Chem 2018;37:1990-1997. © 2018 SETAC. © 2018 SETAC.
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Strategic Munitions Planning in Non-Conventional Asymmetric Operations
2010-04-01
Conventional Asymmetric Operations RTO-MP-SAS-081 16 - 3 with a clearly structured, sized and located military force. The principles of Lanchester ...stockpiles and calculated munitions requirements. REFERENCES [1] Prague Summit Declaration, November 2002. [2] J. Fletcher, The Lanchester Legacy... Lanchester battles, Journal of the Operational Research Society, Vol. 50 No. 3, March 1999. [13] W. Freeman, A Study of Ammunition Consumption, Master of
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Underwater Munitions Expert System: Preliminary Design Report
2015-08-21
analysis would usually be performed, where separation by sieving results in the PMF of sand grain...locations they might potentially aggregate . Furthermore, given knowledge of the types of munitions...feature that Netica provides is the ability to do sensitivity analysis ,
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REMOTE SENSING IN DETECTING BURIED MUNITIONS FROM WORLD WAR I
During World War I, The American University in Washington D.C. was used by the U.S. Army as an experiment station for the development and testing of a variety of battlefield munitions including chemical weapons such as Mustard Gas, Phosgene, Ricin and Lewisite, among othe...
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Disposal of chemical agents and munitions stored at Umatilla Depot Activity, Hermiston, Oregon
Energy Technology Data Exchange (ETDEWEB)
Zimmerman, G.P.; Hillsman, E.L.; Johnson, R.O.; Miller, R.L.; Patton, T.G.; Schoepfle, G.M.; Tolbert, V.R.; Feldman, D.L.; Hunsaker, D.B. Jr.; Kroodsma, R.L.; Morrissey, J.; Rickert, L.W.; Staub, W.P.; West, D.C.
1993-02-01
The Umatilla Depot Activity (UMDA) near Hermiston, Oregon, is one of eight US Army installations in the continental United States where lethal unitary chemical agents and munitions are stored, and where destruction of agents and munitions is proposed under the Chemical Stockpile Disposal Program (CSDP). The chemical agent inventory at UMDA consists of 11.6%, by weight, of the total US stockpile. The destruction of the stockpile is necessary to eliminate the risk to the public from continued storage and to dispose of obsolete and leaking munitions. In 1988 the US Army issued a Final Programmatic Environmental Impact Statement (FPEIS) for the CSDP that identified on-site disposal of agents and munitions as the environmentally preferred alternative (i.e., the alternative with the least potential to cause significant adverse impacts), using a method based on five measures of risk for potential human health and ecosystem/environmental effects; the effectiveness and adequacy of emergency preparedness capabilities also played a key role in the FPEIS selection methodology. In some instances, the FPEIS included generic data and assumptions that were developed to allow a consistent comparison of potential impacts among programmatic alternatives and did not include detailed conditions at each of the eight installations. The purpose of this Phase 1 report is to examine the proposed implementation of on-site disposal at UMDA in light of more recent and more detailed data than those included in the FPEIS. Specifically, this Phase 1 report is intended to either confirm or reject the validity of on-site disposal for the UMDA stockpile. Using the same computation methods as in the FPEIS, new population data were used to compute potential fatalities from hypothetical disposal accidents. Results indicate that onsite disposal is clearly preferable to either continued storage at UMDA or transportation of the UMDA stockpile to another depot for disposal.
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The Political Economy of the Munitions Supply Program
2014-05-01
advantage in production, and further identified which munitions products can be procured offshore with only limited effects on operational liabilities...comparative advantage and access to global supply chains. A few options exist: fixed-price contracts may be indexed to exogenously-given input prices and... franchisees bid their true costs.47 Third, once supply is forthcoming, the franchisee has an incentive to minimize costs unless the franchiser is known
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Munitions having an insensitive detonator system for initiating large failure diameter explosives
Perry, III, William Leroy
2015-08-04
A munition according to a preferred embodiment can include a detonator system having a detonator that is selectively coupled to a microwave source that functions to selectively prime, activate, initiate, and/or sensitize an insensitive explosive material for detonation. The preferred detonator can include an explosive cavity having a barrier within which an insensitive explosive material is disposed and a waveguide coupled to the explosive cavity. The preferred system can further include a microwave source coupled to the waveguide such that microwaves enter the explosive cavity and impinge on the insensitive explosive material to sensitize the explosive material for detonation. In use the preferred embodiments permit the deployment and use of munitions that are maintained in an insensitive state until the actual time of use, thereby substantially preventing unauthorized or unintended detonation thereof.
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Underwater Munitions Expert System to Predict Mobility and Burial
2017-11-14
for predicting the location and possible burial of underwater munitions is required to advise site managers as they plan...that region above the given UXO relative density, which is defined as the UXO density divided by the sand grain density, ( nominally 2650 g...0.0 + 2.5*dsed ; % nominal bed roughness if no burial % (Potentially in future version, ripple height
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National Security Strategy and the Munitions' Paradox: Self-Sufficiency or Maximum Efficiency
National Research Council Canada - National Science Library
McChesney, Michael
1998-01-01
... that the United States military strategy may not be credible to likely regional aggressors. Conversely, DoD acquisition leadership believes industry consolidation should continue and the munitions base should be expanded to include US allies...
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2012-05-01
X Worm Tubifex tubifex X X X Black worm Lumbriculus X Asiatic clam Corbicula fluminea X Estuarine/marine water column Mysid shrimp Americamysis...Objective: Characterize traditional and insensitive munitions (IMs) impacts on amphibian larvae to manage a candidate for T&E status that inhabit
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Characterization of inorganic wastes from metal working industries
International Nuclear Information System (INIS)
Gomez, A.; Viguri, J.R.; Andres, A.; Irabien, A.; Guise, L.; Magalhaes, J.; Castro, F.
1999-01-01
The paper present the results obtained in the characterisation of metalworking wastes, with the sampling of wastes and characterisation data interpretation subjects as the main studied steps. The results of this work allow to establish the environmental impact assessment of the inorganic wastes from a wide range of metalworking processes in order to determine the optimum options to their management (treatment and/or reuses)
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Using waterjet in reverse logistic operations in discarded munitions processing
Czech Academy of Sciences Publication Activity Database
Hloch, S.; Tozan, H.; Yagimli, M.; Valíček, Jan; Rokosz, K.
2011-01-01
Roč. 18, č. 2 (2011), s. 267-271 ISSN 1330-3651 Institutional research plan: CEZ:AV0Z30860518 Keywords : abrasive waterjet * anti tank bullet * automatic line Subject RIV: JQ - Machines ; Tools Impact factor: 0.347, year: 2011 http://hrcak.srce.hr/search/?q=Using+waterjet+in+reverse+logistic+operations+in+discarded+munitions+processing
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International Nuclear Information System (INIS)
Claxton, D.G.S.A.
1988-06-01
The Waste Treatment and Disposal Working Party (WTDWP) covered the areas of: ILW Product Evaluation; ILW and HLW Disposal Studies, and ILW and HLW Quality Checking. The objectives of the programme were to evaluate potential waste products arising from the treatment of ILW/HLW, and to develop appropriate techniques which could be used to check the quality of the finished waste product. (author)
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Briggs, C. W.; Bissonnette, M. C.; Edwards, M.; Shjegstad, S. M.
2016-12-01
Thousands of 100-lb M47A series bombs containing sulfur mustard were disposed in the ocean following World War II yet few studies have been conducted at sites in excess of 250 m, the depth where most discarded military munitions (DMM) were disposed. The Hawai`i Undersea Military Munitions Assessment (HUMMA) project was conducted to evaluate the risk from chemical warfare materiel (CWM) in DMM to human health, measuring ecological differences between the disposal area and nearby but otherwise similar areas, and evaluating the most efficient platforms for surveying DMM sea-disposal sites located at depths between 400-650 m. During the 2014 HUMMA Sampling Survey, the Jason 2 remotely operated vehicle was used to collect data. Shrimp were collected and analyzed to assess the potential for bioaccumulation of CWM, energetics and metals from munitions. No CWM was detected in H. ensifer tissue samples, indicating bioaccumulation is not occurring. Low levels of 2,4,6-trinitrotoluene, 4-amino-2,6-dinitrotoluene, 1,3,5-trinitrobenzene, nitrobenzene, arsenic, copper, and lead were detected and the concentrations were not significantly different at DMM and control sites. No visible deformities, eroded fins, lesions, or tumors were observed on the shrimp living in the vicinity of M47A bombs. Given these results and under current and potential future uses of the HUMMA study area, health risks to likely receptors are within EPA acceptable levels. Photographic data and benthic infauna analysis were used to study benthic organisms that lived on or near munitions. There was no statistically distinguishable difference between organism distributions in dense and sparse munitions fields. Conventional munitions were found to have the greatest number of benthic infauna individuals, with control sites generally having the least number of individuals. This is consistent with the benthic macro-fauna analysis, which shows that munitions provide habitat.
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Methodology for quantification of waste generated in Spanish railway construction works
International Nuclear Information System (INIS)
Guzmán Báez, Ana de; Villoria Sáez, Paola; Río Merino, Mercedes del; García Navarro, Justo
2012-01-01
Highlights: ► Two equations for C and D waste estimation in railway construction works are developed. ► Mixed C and D waste is the most generated category during railway construction works. ► Tunnel construction is essential to quantify the waste generated during the works. ► There is a relationship between C and D waste generated and railway functional units. ► The methodology proposed can be used to obtain new constants for other areas. - Abstract: In the last years, the European Union (EU) has been focused on the reduction of construction and demolition (C and D) waste. Specifically, in 2006, Spain generated roughly 47 million tons of C and D waste, of which only 13.6% was recycled. This situation has lead to the drawing up of many regulations on C and D waste during the past years forcing EU countries to include new measures for waste prevention and recycling. Among these measures, the mandatory obligation to quantify the C and D waste expected to be originated during a construction project is mandated. However, limited data is available on civil engineering projects. Therefore, the aim of this research study is to improve C and D waste management in railway projects, by developing a model for C and D waste quantification. For this purpose, we develop two equations which estimate in advance the amount, both in weight and volume, of the C and D waste likely to be generated in railway construction projects, including the category of C and D waste generated for the entire project.
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Bioconcentration factors and plant-water partition coefficients of munitions compounds in barley.
Torralba-Sanchez, Tifany L; Kuo, Dave T F; Allen, Herbert E; Di Toro, Dominic M
2017-12-01
Plants growing in the soils at military ranges and surrounding locations are exposed, and potentially able to uptake, munitions compounds (MCs). The extent to which a compound is transferred from the environment into organisms such as plants, referred to as bioconcentration, is conventionally measured through uptake experiments with field/synthetic soils. Multiple components/phases that vary among different soil types and affect the bioavailability of the MC, however, hinder the ability to separate the effects of soil characteristics from the MC chemical properties on the resulting plant bioconcentration. To circumvent the problem, this work presents a protocol to measure steady state bioconcentration factors (BCFs) for MCs in barley (Hordeum vulgare L.) using inert laboratory sand rather than field/synthetic soils. Three MCs: 2,4,6-trinitrotoluene (TNT), 2,4-dinitrotoluene (2,4-DNT), and 2,4-dinitroanisole (2,4-DNAN), and two munition-like compounds (MLCs): 4-nitroanisole (4-NAN) and 2-methoxy-5-nitropyridine (2-M-5-NPYNE) were evaluated. Approximately constant plant biomass and exposure concentrations were achieved within a one-month period that produced steady state log BCF values: 0.62 ± 0.02, 0.70 ± 0.03, 1.30 ± 0.06, 0.52 ± 0.03, and 0.40 ± 0.05 L kg plant dwt -1 for TNT, 2,4-DNT, 2,4-DNAN, 4-NAN, and 2-M-5-NPYNE, respectively. Furthermore, results suggest that the upper-bounds of the BCFs can be estimated within an order of magnitude by measuring the partitioning of the compounds between barley biomass and water. This highlights the importance of partition equilibrium as a mechanism for the uptake of MCs and MLCs by barley from interstitial water. The results from this work provide chemically meaningful data for prediction models able to estimate the bioconcentration of these contaminants in plants. Copyright © 2017 Elsevier Ltd. All rights reserved.
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Depleted uranium instead of lead in munitions: the lesser evil.
Jargin, Sergei V
2014-03-01
Uranium has many similarities to lead in its exposure mechanisms, metabolism and target organs. However, lead is more toxic, which is reflected in the threshold limit values. The main potential hazard associated with depleted uranium is inhalation of the aerosols created when a projectile hits an armoured target. A person can be exposed to lead in similar ways. Accidental dangerous exposures can result from contact with both substances. Encountering uranium fragments is of minor significance because of the low penetration depth of alpha particles emitted by uranium: they are unable to penetrate even the superficial keratin layer of human skin. An additional cancer risk attributable to the uranium exposure might be significant only in case of prolonged contact of the contaminant with susceptible tissues. Lead intoxication can be observed in the wounded, in workers manufacturing munitions etc; moreover, lead has been documented to have a negative impact on the intellectual function of children at very low blood concentrations. It is concluded on the basis of the literature overview that replacement of lead by depleted uranium in munitions would be environmentally beneficial or largely insignificant because both lead and uranium are present in the environment.
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Depleted uranium instead of lead in munitions: the lesser evil
International Nuclear Information System (INIS)
Jargin, Sergei V
2014-01-01
Uranium has many similarities to lead in its exposure mechanisms, metabolism and target organs. However, lead is more toxic, which is reflected in the threshold limit values. The main potential hazard associated with depleted uranium is inhalation of the aerosols created when a projectile hits an armoured target. A person can be exposed to lead in similar ways. Accidental dangerous exposures can result from contact with both substances. Encountering uranium fragments is of minor significance because of the low penetration depth of alpha particles emitted by uranium: they are unable to penetrate even the superficial keratin layer of human skin. An additional cancer risk attributable to the uranium exposure might be significant only in case of prolonged contact of the contaminant with susceptible tissues. Lead intoxication can be observed in the wounded, in workers manufacturing munitions etc; moreover, lead has been documented to have a negative impact on the intellectual function of children at very low blood concentrations. It is concluded on the basis of the literature overview that replacement of lead by depleted uranium in munitions would be environmentally beneficial or largely insignificant because both lead and uranium are present in the environment. (opinion)
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International Nuclear Information System (INIS)
Warhus, J.; Castleton, R.; Lanning, S.
1981-12-01
Testing and quality assurance of large numbers of firing systems are an essential part of the development of the Tactical Airfield Attack Munition (TAAM). A computerized test and data acquisition system has been developed to make the testing and quality assurance workload manageable. The system hardware utilizes an LSI-11/23 computer, a Tektronix 7612 transient digitizer, and various other programmable instruments and power supplies. The system is capable of measuring and analyzing mechanical shock and fireset transient waveforms, automating testing sequences, and making records and comparisons of the test results. The system architecture is flexible for general purpose firing system development work
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Women waste pickers: living conditions, work, and health.
Coelho, Alexa Pupiara Flores; Beck, Carmem Lúcia Colomé; Fernandes, Marcelo Nunes da Silva; Freitas, Natiellen Quatrin; Prestes, Francine Cassol; Tonel, Juliana Zancan
2016-09-29
To know the elements of work, health, and living conditions of women who pick recyclable waste and are members of a waste cooperative in a town of the state of Rio Grande do Sul, Brazil. This is a qualitative, exploratory and descriptive study with seven subjects. Data were collected through participative observation, semi structured interview, and a focus group from July to August of 2013. The data were subjected to content analysis. The following thematic categories emerged: Women's work, informality and precariousness; Experiences of job satisfaction; and Working conditions and health: experiences with accidents, illness and health services. It was concluded that the women who collect recyclable material are exposed to precarious work conditions and potential health risks, such as work overload, accidents, illness, and social insecurity, and that nurses are responsible for promoting actions that ensure the health and inclusion of these workers.
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Decision Support Tools for Munitions Response Performance Prediction and Risk Assessment
2016-09-01
Oldenburg. A discrimination algorithm for UXO using time domain electromagnetic induction . Journal of Environmental and Engineering Geophysics, 6:91...the course of a munitions response project. Unexploded ordnance (UXO), electromagnetic (EM), sensors, electromagnetic induction (EMI), data...approach defines a detection channel that is a linear combination of received channels. The weightings of received channels comprising the optimized
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Energy Technology Data Exchange (ETDEWEB)
Fellows, R.J.; Harvey, S.D.; Cataldo, D.A.
1995-09-01
The goals of this effort were to confirm and expand data related to the behavior and impacts of munitions residues upon human food chain components. Plant species employed included corn (Zea mays), alfalfa (Medicago sativa). spinach (Spinacea oleraceae), and carrot (Daucus carota). Plants were grown from seed to maturity (70 to 120 days) in a low-fertility soil (Burbank) amended with either {sup 14}C-TNT or {sup 14}C-RDX at which time they were harvested and analyzed for munitions uptake, partitioning, and chemical form of the munition or munition-metabolite. All four of the plant species used in this study accumulated the {sup 14}C-TNT- and RDX-derived label. The carrot, alfalfa, and corn demonstrated a higher percentage of label retained in the roots (62, 73, and 83% respectively). The spinach contained less activity in its root (36%) but also contained the highest TNT specific activity observed (>4600 jig TNT equivalents/g dry wt.). The specific uptake values of RDX for the spinach and alfalfa were comparable to those previously reported for wheat and bean (314 to 590 {mu}g RDX-equivalents/g dry wt. respectively). An exception to this may be the carrot where the specific activity was found to exceed 4200 {mu}g RDX-equivalents/g dry wt. in the shoot. The total accumulation of TNT by the plants ranged from 1.24% for the spinach to 2.34% for the carrot. The RDX plants ranging from 15% for the spinach to 37% for the carrot. There was no identifiable TNT or amino dinitrotoluene (ADNT) isomers present in the plants however, the parent RDX compound was found at significant levels in the shoot of alfalfa (> 1 80 {mu}g/g) and corn (>18 {mu}g/g).
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Waste management project fiscal year 1998 multi-year work plan WBS 1.2
International Nuclear Information System (INIS)
Slaybaugh, R.R.
1997-08-01
The MYWP technical baseline describes the work to be accomplished by the Project and the technical standards which govern that work. The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposition of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project (SW), Liquid Effluents Project (LEP), and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible. The paper tabulates the major facilities that interface with this Project, identifying the major facilities that generate waste, materials, or infrastructure for this Project and the major facilities that will receive waste and materials from this Project
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Waste management project fiscal year 1998 multi-year work plan WBS 1.2
Energy Technology Data Exchange (ETDEWEB)
Slaybaugh, R.R.
1997-08-29
The MYWP technical baseline describes the work to be accomplished by the Project and the technical standards which govern that work. The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposition of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project (SW), Liquid Effluents Project (LEP), and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible. The paper tabulates the major facilities that interface with this Project, identifying the major facilities that generate waste, materials, or infrastructure for this Project and the major facilities that will receive waste and materials from this Project.
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International Nuclear Information System (INIS)
Claxton, D.G.S.A.
1989-05-01
The report covers progress in the area of ILW Product Evaluation. This work is a continuation of a generic study programme directed by the Waste Treatment and Disposal Working Party. The objective of the programme was to evaluate potential waste products arising from the treatment of ILW. (author)
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Energy Technology Data Exchange (ETDEWEB)
Ensminger, J.T.; Hillsman, E.L.; Johnson, R.D.; Morrisey, J.A.; Staub, W.P.; Boston, C.R.; Hunsaker, D.B.; Leibsch, E.; Rickert, L.W.; Tolbert, V.R.; Zimmerman, G.P.
1991-09-01
The Pine Bluff Arsenal (PBA) near Pine Bluff, Arkansas, is one of eight continental United States (CONUS) Army installations where lethal unitary chemical agents and munitions are stored and where destruction of agents and munitions is proposed under the Chemical Stockpile Disposal Program (CSDP). The chemical agent inventory at PBA consists of approximately 12%, by weight, of the total US stockpile. The destruction of the stockpile is necessary to eliminate the risk to the public from continued storage and to dispose of obsolete and leaking munitions. In 1988 the US Army issued a Final Programmatic Environmental Impact Statement (FPEIS) for the CSDP that identified on-site disposal of agents and munitions as the environmentally preferred alternative (i.e., the alternative with the least potential to cause significant adverse impacts). The purpose of this report is to examine the proposed implementation of on-site disposal at PBA in light of more recent and more detailed data than those on which the FPEIS is based. New population data were used to compute fatalities using the same computation methods and values for all other parameters as in the FPEIS. Results indicate that all alternatives are indistinguishable when the potential health impacts to the PBA community are considered. However, risks from on-site disposal are in all cases equal to or less than risks from other alternatives. Furthermore, no unique resources with the potential to prevent or delay implementation of on-site disposal at PBA have been identified.
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National Research Council Canada - National Science Library
Floersheim, Bruce; Hou, Gene
2006-01-01
... mechanism for a number of vehicles caught in the killzone. Thus, it is useful to study and attempt to model through equations and simulation the interaction between enemy agents and these new munitions...
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Cost Of Compliance On Munitions Consolidation From Lualualei To West Loch
2017-12-01
well as the opportunity to drastically reduce the transportation of ordnance to and from the Lualualei Annex through local community roads and areas...single road and the availability of CULT trucks and/or drivers that could impede an expeditious response in a contingency operation. This project...to distribute munitions to the fleet. This consolidation plan will also reduce the infrastructure costs for ordnance storage, maintenance , and
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Dissolution of NTO, DNAN, and Insensitive Munitions Formulations and Their Fates in Soils
2014-09-01
plastic bags to save the (a) (b) ERDC/CRREL TR-14-23 10 sample even if the bottle should break from ice formation. During each collection, we...Bacillus sp. Biodegradation 23 (2): 287–295. Prak, D.L., and D. O’Sullivan. 2012. Photochemical Transformation of Munitions Constituents in Marine
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Tank waste remediation system multi-year work plan
International Nuclear Information System (INIS)
1994-09-01
The Tank Waste Remediation System (TWRS) Multi-Year Work Plan (MYWP) documents the detailed total Program baseline and was constructed to guide Program execution. The TWRS MYWP is one of two elements that comprise the TWRS Program Management Plan. The TWRS MYWP fulfills the Hanford Site Management System requirement for a Multi-Year Program Plan and a Fiscal-Year Work Plan. The MYWP addresses program vision, mission, objectives, strategy, functions and requirements, risks, decisions, assumptions, constraints, structure, logic, schedule, resource requirements, and waste generation and disposition. Sections 1 through 6, Section 8, and the appendixes provide program-wide information. Section 7 includes a subsection for each of the nine program elements that comprise the TWRS Program. The foundation of any program baseline is base planning data (e.g., defendable product definition, logic, schedules, cost estimates, and bases of estimates). The TWRS Program continues to improve base data. As data improve, so will program element planning, integration between program elements, integration outside of the TWRS Program, and the overall quality of the TWRS MYWP. The MYWP establishes the TWRS baseline objectives to store, treat, and immobilize highly radioactive Hanford waste in an environmentally sound, safe, and cost-effective manner. The TWRS Program will complete the baseline mission in 2040 and will incur costs totalling approximately 40 billion dollars. The summary strategy is to meet the above objectives by using a robust systems engineering effort, placing the highest possible priority on safety and environmental protection; encouraging open-quotes out sourcingclose quotes of the work to the extent practical; and managing significant but limited resources to move toward final disposition of tank wastes, while openly communicating with all interested stakeholders
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Tank waste remediation system multi-year work plan
Energy Technology Data Exchange (ETDEWEB)
1994-09-01
The Tank Waste Remediation System (TWRS) Multi-Year Work Plan (MYWP) documents the detailed total Program baseline and was constructed to guide Program execution. The TWRS MYWP is one of two elements that comprise the TWRS Program Management Plan. The TWRS MYWP fulfills the Hanford Site Management System requirement for a Multi-Year Program Plan and a Fiscal-Year Work Plan. The MYWP addresses program vision, mission, objectives, strategy, functions and requirements, risks, decisions, assumptions, constraints, structure, logic, schedule, resource requirements, and waste generation and disposition. Sections 1 through 6, Section 8, and the appendixes provide program-wide information. Section 7 includes a subsection for each of the nine program elements that comprise the TWRS Program. The foundation of any program baseline is base planning data (e.g., defendable product definition, logic, schedules, cost estimates, and bases of estimates). The TWRS Program continues to improve base data. As data improve, so will program element planning, integration between program elements, integration outside of the TWRS Program, and the overall quality of the TWRS MYWP. The MYWP establishes the TWRS baseline objectives to store, treat, and immobilize highly radioactive Hanford waste in an environmentally sound, safe, and cost-effective manner. The TWRS Program will complete the baseline mission in 2040 and will incur costs totalling approximately 40 billion dollars. The summary strategy is to meet the above objectives by using a robust systems engineering effort, placing the highest possible priority on safety and environmental protection; encouraging {open_quotes}out sourcing{close_quotes} of the work to the extent practical; and managing significant but limited resources to move toward final disposition of tank wastes, while openly communicating with all interested stakeholders.
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Waste Contaminants at Military Bases Working Group report
International Nuclear Information System (INIS)
1993-01-01
The Waste Contaminants at Military Bases Working Group has screened six prospective demonstration projects for consideration by the Federal Advisory Committee to Develop On-Site Innovative Technologies (DOIT). These projects include the Kirtland Air Force Base Demonstration Project, the March Air Force Base Demonstration Project, the McClellan Air Force Base Demonstration Project, the Williams Air Force Base Demonstration Project, and two demonstration projects under the Air Force Center for Environmental Excellence. A seventh project (Port Hueneme Naval Construction Battalion Center) was added to list of prospective demonstrations after the September 1993 Working Group Meeting. This demonstration project has not been screened by the working group. Two additional Air Force remediation programs are also under consideration and are described in Section 6 of this document. The following information on prospective demonstrations was collected by the Waste Contaminants at Military Bases Working Group to assist the DOIT Committee in making Phase 1 Demonstration Project recommendations. The remainder of this report is organized into seven sections: Work Group Charter's mission and vision; contamination problems, current technology limitations, and institutional and regulatory barriers to technology development and commercialization, and work force issues; screening process for initial Phase 1 demonstration technologies and sites; demonstration descriptions -- good matches;demonstration descriptions -- close matches; additional candidate demonstration projects; and next steps
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International Nuclear Information System (INIS)
Claxton, D.G.S.A.
1986-01-01
The Waste Treatment and Disposal Working Party (WTDWP) covered the areas of: ILW Product Evaluation, ILW and HLW Disposal Studies and ILW and HLW Quality Checking. The objectives of the programme were to evaluate potential waste products arising from the treatment of ILW, and to develop appropriate techniques which could be used to check the quality of the finished waste product. (author)
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Process development work plan for waste feed delivery system
International Nuclear Information System (INIS)
Papp, I.G.
1998-01-01
This work plan defines the process used to develop project definition for Waste Feed Delivery (WFD). Project definition provides the direction for development of definitive design media required for the ultimate implementation of operational processing hardware and software. Outlines for the major deliverables are attached as appendices. The implementation of hardware and software will accommodate requirements for safe retrieval and delivery of waste currently stored in Hanford's underground storage tanks. Operations and maintenance ensure the availability of systems, structures, and components for current and future planned operations within the boundary of the Tank Waste Remediation System (TWRS) authorization basis
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WIPP Facility Work Plan for Solid Waste Management Units
International Nuclear Information System (INIS)
2000-01-01
This Facility Work Plan (FWP) has been prepared as required by Module VII,Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a). This work plan describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current New Mexico Environment Department (NMED) guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility's's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit. The scope of work for the RFI Work Plan or SAP is being developed by the Permittees. The final content of the RFI Work Plan or SAP will be coordinated with the NMED for submittal on May 24, 2000. Specific project-related planning information will be included in the RFI Work Plan or SAP. The SWMU program at WIPP began in 1994 under U.S. Environmental Protection Agency (EPA) regulatory authority. NMED subsequently received regulatory authority from EPA. A
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WIPP Facility Work Plan for Solid Waste Management Units
Energy Technology Data Exchange (ETDEWEB)
Washington TRU Solutions LLC
2000-02-25
This Facility Work Plan (FWP) has been prepared as required by Module VII,Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a). This work plan describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current New Mexico Environment Department (NMED) guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility’s Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to NMED’s guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit. The scope of work for the RFI Work Plan or SAP is being developed by the Permittees. The final content of the RFI Work Plan or SAP will be coordinated with the NMED for submittal on May 24, 2000. Specific project-related planning information will be included in the RFI Work Plan or SAP. The SWMU program at WIPP began in 1994 under U.S. Environmental Protection Agency (EPA) regulatory authority. NMED subsequently received regulatory authority from EPA
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Energy Technology Data Exchange (ETDEWEB)
Zimmerman, G.P.; Hillsman, E.L.; Johnson, R.O.; Miller, R.L.; Patton, T.G.; Schoepfle, G.M.; Tolbert, V.R.; Feldman, D.L.; Hunsaker, D.B. Jr.; Kroodsma, R.L.; Morrissey, J.; Rickert, L.W.; Staub, W.P.; West, D.C.
1993-02-01
The Umatilla Depot Activity (UMDA) near Hermiston, Oregon, is one of eight US Army installations in the continental United States where lethal unitary chemical agents and munitions are stored, and where destruction of agents and munitions is proposed under the Chemical Stockpile Disposal Program (CSDP). The chemical agent inventory at UMDA consists of 11.6%, by weight, of the total US stockpile. The destruction of the stockpile is necessary to eliminate the risk to the public from continued storage and to dispose of obsolete and leaking munitions. In 1988 the US Army issued a Final Programmatic Environmental Impact Statement (FPEIS) for the CSDP that identified on-site disposal of agents and munitions as the environmentally preferred alternative (i.e., the alternative with the least potential to cause significant adverse impacts), using a method based on five measures of risk for potential human health and ecosystem/environmental effects; the effectiveness and adequacy of emergency preparedness capabilities also played a key role in the FPEIS selection methodology. In some instances, the FPEIS included generic data and assumptions that were developed to allow a consistent comparison of potential impacts among programmatic alternatives and did not include detailed conditions at each of the eight installations. The purpose of this Phase 1 report is to examine the proposed implementation of on-site disposal at UMDA in light of more recent and more detailed data than those included in the FPEIS. Specifically, this Phase 1 report is intended to either confirm or reject the validity of on-site disposal for the UMDA stockpile. Using the same computation methods as in the FPEIS, new population data were used to compute potential fatalities from hypothetical disposal accidents. Results indicate that onsite disposal is clearly preferable to either continued storage at UMDA or transportation of the UMDA stockpile to another depot for disposal.
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DEFF Research Database (Denmark)
Mohammed Abdullah Christensen, Ilias; Sanderson, Hans; Baatrup, Erik
2016-01-01
As a result of the disarmament of Germany after the Second World War, 65,000 tons of chemical munitions were dumped in the Baltic Sea. Approximately 13,000 tons containing chemical warfare agents (CWAs) of which 11,000 tons were dumped in the Bornholm Basin east of Bornholm. This paper addresses...
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The Productivity Of Working Hours
John Pencavel
2013-01-01
Observations on munition workers, most of them women, are organized to examine the relationship between their output and their working hours. The relationship is nonlinear: below an hours threshold, output is proportional to hours; above a threshold, output rises at a decreasing rate as hours increase. Implications of these results for the estimation of labor supply functions are taken up. The findings also link up with current research on the effects of long working hours on accidents and in...
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WIPP Facility Work Plan for Solid Waste Management Units
Energy Technology Data Exchange (ETDEWEB)
Washington TRU Solutions LLC
2001-02-25
This 2001 Facility Work Plan (FWP) has been prepared as required by Module VII, Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a), and incorporates comments from the New Mexico Environment Department (NMED) received on December 6, 2000 (NMED, 2000a). This February 2001 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. The permittees are evaluating data from previous investigations of the SWMUs and AOCs against the newest guidance proposed by the NMED. Based on these data, the permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility’s Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit.
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International Nuclear Information System (INIS)
Claxton, D.G.S.A.
1985-01-01
The progress report from the waste treatment and disposal working party is concerned with the management of intermediate-level radioactive waste arising from dismantled fuel assemblies, cladding removed from fuel cans, sludges from fuel cladding corrosion, flocs from liquid waste, ion exchange resins and solid wastes generated during reprocessing. It is proposed that these wastes be incorporated in a matrix for safe transport, storage and disposal and the objectives of the study are to evaluate waste products arising from the treatment of ILWS and to develop techniques to check the quality of the finished waste product. (UK)
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Energy Technology Data Exchange (ETDEWEB)
Duijm, N.J.; Markert, F. [Forskningscenter Risoe (Denmark)
2000-03-01
Modern technologies like high-pressure water washout and Fluidised Bed Combustion provide safe and environmentally acceptable solutions for demilitarisation. The environmental impact from the traditional techniques Open Burning and Open Detonation can be drastically reduced. High-pressure water washout in combination with Fluidised Bed Combustion and NO{sub x}-reduction using urea-injection is the best well-demonstrated technology considered in this study. This technology can be used for large/medium sized calibre munitions, but additional removal of NO{sub x} from the flue gases is required in order to comply with European emission standards. It has been made credible at existing Rotary Kilns used for hazardous waste in general can be used also for incineration of de-sensitised, down sized munitions (slurries), with a similar performance with respect to environmental and safety aspects as Fluidised Bed Combustion. Using a Closed Detonation chamber with flue-gas cleaning has important environmental advantages compared to Open Burning and Open Detonation, especially for small munitions (e.g. fuzes, antipersonnel mines, pyrotechnics). However, because Closed Detonation is labour-intensive and requires operation of complex, pressurised systems, it poses more risk on the personnel. For that reason, it is recommended to develop other systems to demilitarise small munitions. It appears that the air pollution emissions from transport of munitions to disposal facilities is significant compared to the process emissions of the 'cleanest' technologies. Similarly, risks related to transport (due to ordinary accidents involving trucks) are not dominating, but cannot be ignored compared to process risks. These considerations need to be included when comparing less sophisticated local or mobile facilities with central facilities having advanced flue gas cleaning. (au)
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International Nuclear Information System (INIS)
Higson, S.G.
1984-01-01
The subject is covered in paragraphs: introduction (arisings of intermediate-level radioactive waste); organisation and role of the Waste Treatment and Disposal Working Party; main objectives (to provide data on intermediate-level waste treatment systems and allow assessment of alternative processes); ILW process and flowsheeting studies; ILW product evaluation. (U.K.)
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Waste Management Project fiscal year 1998 multi-year work plan, WBS 1.2
International Nuclear Information System (INIS)
Jacobsen, P.H.
1997-01-01
The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposal of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project, Liquid Effluents Project, and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible
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Work plan for waste receiving and processing module 2A waste characterization study
International Nuclear Information System (INIS)
Bergeson, C.L.
1994-11-01
This WRAP 2A Waste Characterization Study effort addresses those certification strategy functions related to characterization by defining criteria associated with each function, identifying administrative and design mechanisms for accomplishing each of these functions and evaluating alternatives where applicable. This work plan provides direction for completing the study
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2009-11-01
CEQ Council on Environmental Quality CFR Code of Federal Regulations CO Carbon Monoxide cpm Counts per Minute CRM Cultural Resource Manager...newspaper advertisement in the Rapid City Journal announcing the availability of the Draft EA for a 30-day public and agency review to facilitate...Ellsworth Air Force Base Munitions Storage Area Environmental Assessment Page 2-5 public involvement in the project. This advertisement was published one
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Energy Technology Data Exchange (ETDEWEB)
LaJeunesse, C.A.; Chan, Jennifer P.; Raber, T.N.; Macmillan, D.C.; Rice, S.F.; Tschritter, K.L.
1993-11-01
The existing demilitarization stockpile contains large quantities of colored smoke, spotting dye, and pyrotechnic munitions. For many years, these munitions have been stored in magazines at locations within the continental United States awaiting completion of the life-cycle. The open air burning of these munitions has been shown to produce toxic gases that are detrimental to human health and harmful to the environment. Prior efforts to incinerate these compositions have also produced toxic emissions and have been unsuccessful. Supercritical water oxidation (SCWO) is a rapidly developing hazardous waste treatment method that can be an alternative to incineration for many types of wastes. The primary advantage SCWO affords for the treatment of this selected set of obsolete munitions is that toxic gas and particulate emissions will not occur as part of the effluent stream. Sandia is currently designing a SCWO reactor for the US Army Armament Research, Development & Engineering Center (ARDEC) to destroy colored smoke, spotting dye, and pyrotechnic munitions. This report summarizes the design status of the ARDEC reactor. Process and equipment operation parameters, process flow equations or mass balances, and utility requirements for six wastes of interest are developed in this report. Two conceptual designs are also developed with all process and instrumentation detailed.
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DuVal, C.; Carton, G.; Trembanis, A. C.; Edwards, M.; Miller, J. K.
2017-12-01
Munitions and explosives of concern (MEC) are present in U.S. waters as a result of past and ongoing live-fire testing and training, combat operations, and sea disposal. To identify MEC that may pose a risk to human safety during development of offshore wind facilities on the Atlantic Outer Continental Shelf (OCS), the Bureau of Ocean Energy Management (BOEM) is preparing to develop guidance on risk analysis and selection processes for methods and technologies to identify MEC in Wind Energy Areas (WEA). This study developed a process for selecting appropriate technologies and methodologies for MEC detection using a synthesis of historical research, physical site characterization, remote sensing technology review, and in-field trials. Personnel were tasked with seeding a portion of the Delaware WEA with munitions surrogates, while a second group of researchers not privy to the surrogate locations tested and optimized the selected methodology to find and identify the placed targets. This in-field trial, conducted in July 2016, emphasized the use of multiple sensors for MEC detection, and led to further guidance for future MEC detection efforts on the Atlantic OCS. An April 2017 follow on study determined the fate of the munitions surrogates after the Atlantic storm season had passed. Using regional hydrodynamic models and incorporating the recommendations from the 2016 field trial, the follow on study examined the fate of the MEC and compared the findings to existing research on munitions mobility, as well as models developed as part of the Office of Naval Research Mine-Burial Program. Focus was given to characterizing the influence of sediment type on surrogate munitions behavior and the influence of mophodynamics and object burial on MEC detection. Supporting Mine-Burial models, ripple bedforms were observed to impede surrogate scour and burial in coarse sediments, while surrogate burial was both predicted and observed in finer sediments. Further, incorporation of
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National Research Council Canada - National Science Library
Von Stackleberg, Katherine; Amos, Craig; Butler, C; Smith, Thomas; Famely, J; McArdle, M; Southworth, B; Steevens, Jeffrey
2006-01-01
...) associated with munitions. This study evaluates the potential long-term impacts on selected threatened and endangered species resulting from dispersion and deposition of vapors and particles found in the fog oils...
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2017-09-01
and explosives of concern (MEC) corroding, breaching, and leaking MC into the water column (Darrach, Chutjian, and Plett, 1998; GMI, 2007; Lewis et...underwater UWMM have the potential to corrode, breach, and leak munitions constituents (MCs) such as 2,4,6-trinitrotoluene (TNT) and hexahydro-1,3,5...Wang et al., 2013), a number of challenges prevent accurate assessment of environmental exposure using traditional water , sediment, and tissue
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Waste disposal in the deep ocean: An overview
International Nuclear Information System (INIS)
O'Connor, T.P.; Kester, D.R.; Burt, W.V.; Capuzzo, J.M.; Park, P.K.; Duedall, I.W.
1985-01-01
Incineration at sea, industrial and sewage waste disposal in the surface mixing zone, and disposal of low-level nuclear wastes, obsolete munitions, and nerve gas onto the seafloor have been the main uses of the deep sea for waste management. In 1981 the wastes disposed of in the deep sea consisted of 48 X 10/sup 4/ t of liquid industrial wastes and 2 X 10/sup 4/ t of sewage sludge by the United States; 1.5 X 10/sup 4/ t (solids) of sewage sludge by the Federal Republic of German; 5300 t of liquid industrial wastes by Denmark; 99 t of solid industrial wastes by the United Kingdom; and 9400 t of low-level radioactive wastes by several European countries. Also in 1981 at-sea incineration of slightly more than 10/sup 5/ t of organic wastes from Belgium, France, the Federal Republic of Germany, the Netherlands, Norway, Sweden, and the United Kingdom was carried out in the North Sea. Unique oceanographic features of the deep sea include its large dilution capacity; the long residence time of deep-sea water (on the order of 10/sup 2/ y); low biological productivity in the surface water of the open ocean (≅50 g m/sup -2/ of carbon per year); the existence of an oxygen minimum zone at several hundred meters deep in the mid-latitudes; and the abyssal-clay regions showing sedimentary records of tens of millions of years of slow, uninterrupted deposition of fine-grained clay. Any deep-sea waste disposal strategy must take into account oceanic processes and current scientific knowledge in order to attain a safe solution that will last for centuries
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Fares, Jawad; Gebeily, Souheil; Saad, Mohamad; Harati, Hayat; Nabha, Sanaa; Said, Najwane; Kanso, Mohamad; Abdel Rassoul, Ronza; Fares, Youssef
2017-08-18
This study aims to explore the short-term and long-term prevalence and effects of post-traumatic stress disorder (PTSD) among victims of cluster munitions. A prospective 10-year longitudinal study that took place in Lebanon. Two-hundred-and-forty-four Lebanese civilian victims of submunition blasts, who were injured in 2006 and were over 18 years old, were interviewed. Included were participants who had been diagnosed with PTSD according to the Diagnostic and Statistical Manual of Mental Disorders, 5th Edition (DSM-5) and the PTSD Checklist - Civilian Version in 2006. Interviewees were present for the 10-year follow-up. PTSD prevalence rates of participants in 2006 and 2016 were compared. Analysis of the demographical data pertaining to the association of long-term PTSD with other variables was performed. p Values <0.05 were considered statistically significant for all analyses (95% CI). All the 244 civilians injured by cluster munitions in 2006 responded, and were present for long-term follow-up in 2016. The prevalence of PTSD decreased significantly from 98% to 43% after 10 years (p<0.001). A lower long-term prevalence was significantly associated with male sex (p<0.001), family support (p<0.001) and religion (p<0.001). Hospitalisation (p=0.005) and severe functional impairment (p<0.001) post-trauma were significantly associated with increased prevalence of long-term PTSD. Symptoms of negative cognition and mood were more common in the long run. In addition, job instability was the most frequent socioeconomic repercussion among the participants (88%). Psychological symptoms, especially PTSD, remain high in war-affected populations many years after the war; this is particularly evident for Lebanese civilians who were victimised by cluster munitions. Screening programmes and psychological interventions need to be implemented in vulnerable populations exposed to war traumas. Officials and public health advocates should consider the socioeconomic implications, and
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Reduced waste generation technical work plan
International Nuclear Information System (INIS)
1987-05-01
The United States Department of Energy has established policies for avoiding plutonium losses to the waste streams and minimizing the generation of wastes produced at its nuclear facilities. This policy is evidenced in DOE Order 5820.2, which states ''Technical and administrative controls shall be directed towards reducing the gross volume of TRU waste generated and the amount of radioactivity in such waste.'' To comply with the DOE directive, the Defense Transuranic Waste Program (DTWP) supports and provides funding for specific research and development tasks at the various DOE sites to reduce the generation of waste. This document has been prepared to give an overview of current and past Reduced Waste Generation task activities which are to be based on technical and cost/benefit factors. The document is updated annually, or as needed, to reflect the status of program direction. Reduced Waste Generation (RWG) tasks encompass a wide range of goals which are basically oriented toward (1) avoiding the generation of waste, (2) changing processes or operations to reduce waste, (3) converting TRU waste into LLW by sorting or decontamination, and (4) reducing volumes through operations such as incineration or compaction
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International Nuclear Information System (INIS)
Morris, M.I.; Conley, T.B.; Osborne-Lee, I.W.
1997-01-01
May 1996, the U.S. Department of Energy (DOE) Mixed Waste Focus Area (MWFA) initiated the Mercury Work Group (HgWG). The HgWG was established to address and resolve the issues associated with Mercury- contaminated mixed wastes (MWs). During the initial technical baseline development process of the MWFA, three of the top four technology deficiencies identified were related to (1) amalgamation, (2) stabilization, and (3) separation and removal for the treatment of mercury and mercury-contaminated mixed waste (MW). The HgWG is assisting the MWFA in soliciting, identifying, initiating, and managing efforts to address these needs
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Gurtowski, Luke A; Griggs, Chris S; Gude, Veera G; Shukla, Manoj K
2018-02-01
This manuscript reports results of combined computational chemistry and batch adsorption investigation of insensitive munition compounds, 2,4-dinitroanisole (DNAN), triaminotrinitrobenzene (TATB), 1,1-diamino-2,2-dinitroethene (FOX-7) and nitroguanidine (NQ), and traditional munition compound 2,4,6-trinitrotoluene (TNT) on the surfaces of cellulose, cellulose triacetate, chitin and chitosan biopolymers. Cellulose, cellulose triacetate, chitin and chitosan were modeled as trimeric form of the linear chain of 4 C 1 chair conformation of β-d-glucopyranos, its triacetate form, β-N-acetylglucosamine and D-glucosamine, respectively, in the 1➔4 linkage. Geometries were optimized at the M062X functional level of the density functional theory (DFT) using the 6-31G(d,p) basis set in the gas phase and in the bulk water solution using the conductor-like polarizable continuum model (CPCM) approach. The nature of potential energy surfaces of the optimized geometries were ascertained through the harmonic vibrational frequency analysis. The basis set superposition error (BSSE) corrected interaction energies were obtained using the 6-311G(d,p) basis set at the same theoretical level. The computed BSSE in the gas phase was used to correct interaction energy in the bulk water solution. Computed and experimental results regarding the ability of considered surfaces in adsorbing the insensitive munitions compounds are discussed. Copyright © 2017. Published by Elsevier B.V.
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Rezende-Neto, Joao; Silva, Fabriccio Df; Porto, Leonardo Bo; Teixeira, Luiz C; Tien, Homer; Rizoli, Sandro B
2009-06-26
We present the case of a patient who sustained a penetrating injury to the chest caused by an attenuated energy rubber bullet and review the literature on thoracic injuries caused by plastic and rubber "less-lethal" munitions. The patient of this report underwent a right thoracotomy to extract the projectile as well as a wedge resection of the injured lung parenchyma. This case demonstrates that even supposedly safe riot control munition fired at close range, at the torso, can provoke serious injury. Therefore a thorough investigation and close clinical supervision are justified.
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Energy Technology Data Exchange (ETDEWEB)
Nutt, M.; Nuclear Engineering Division
2010-05-25
The activity of Phase I of the Waste Management Working Group under the United States - Japan Joint Nuclear Energy Action Plan started in 2007. The US-Japan JNEAP is a bilateral collaborative framework to support the global implementation of safe, secure, and sustainable, nuclear fuel cycles (referred to in this document as fuel cycles). The Waste Management Working Group was established by strong interest of both parties, which arise from the recognition that development and optimization of waste management and disposal system(s) are central issues of the present and future nuclear fuel cycles. This report summarizes the activity of the Waste Management Working Group that focused on consolidation of the existing technical basis between the U.S. and Japan and the joint development of a plan for future collaborative activities. Firstly, the political/regulatory frameworks related to nuclear fuel cycles in both countries were reviewed. The various advanced fuel cycle scenarios that have been considered in both countries were then surveyed and summarized. The working group established the working reference scenario for the future cooperative activity that corresponds to a fuel cycle scenario being considered both in Japan and the U.S. This working scenario involves transitioning from a once-through fuel cycle utilizing light water reactors to a one-pass uranium-plutonium fuel recycle in light water reactors to a combination of light water reactors and fast reactors with plutonium, uranium, and minor actinide recycle, ultimately concluding with multiple recycle passes primarily using fast reactors. Considering the scenario, current and future expected waste streams, treatment and inventory were discussed, and the relevant information was summarized. Second, the waste management/disposal system optimization was discussed. Repository system concepts were reviewed, repository design concepts for the various classifications of nuclear waste were summarized, and the factors
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National Research Council Canada - National Science Library
Ezal, Kenan; Agate, Craig
2006-01-01
This paper considers the problem of tracking and intercepting a potentially moving ground-based RF source with an autonomous guided munition that has a passive bearings-only sensor located on its nose...
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Elizar, Suripin, Wibowo, Mochamad Agung
2017-11-01
Delays in construction sites occur due to systematic additions of time waste in various activities that are part of the construction process. Work-time waste is non-adding value activity which used to differentiate between physical construction waste found on site and other waste which occurs during the construction process. The aim of this study is identification using the concept of Value Stream Mapping (VSM) to reduce of work-time waste as applied the smart construction management.VSM analysis is a method of business process improvement. The application of VSM began in the manufacturing community. The research method base on theoretically informed case study and literature review. The data have collected using questionnaire through personal interviews from 383 respondents on construction project in Indonesia. The results show that concept of VSM can identify causes of work-time waste. Base on result of questioners and quantitative approach analysis was obtained 29 variables that influence of work-time waste or non-value-adding activities. Base on three cases of construction project founded that average 14.88% of working time was classified as waste. Finally, the concept of VSM can recommend to identification of systematic for reveal current practices and opportunities for improvement towards global challenges. The concept of value stream mapping can help optimize to reduce work-time waste and improve quality standard of construction management. The concept is also can help manager to make a decision to reduce work-time waste so as to obtain of result in more efficient for performance and sustainable construction project.
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The Waste Treatment Plant, a Work in Progress
International Nuclear Information System (INIS)
Hamel, W. F. Jr.; Duncan, G. M.
2006-01-01
There are many challenges in the design and construction of Department of Energy's (DOE) Waste Treatment and Immobilization Plant (WTP) at the Hanford site. The plant is being built to process some 55 million gallons of radioactive waste from 177 underground tanks. Engineering and construction are progressing on this largest project in the DOE complex. This paper describes some of WTP's principal recent challenges and opportunities and how they are being addressed to minimize impact on the project, enhance the capabilities of the facilities, and reduce risk. A significant new development in 2005 was the need to account for higher seismic accelerations than originally specified for the facility structures and equipment. Efforts have centered on continuing design and construction with minimal risk, while the final seismic design spectra was developed. Other challenges include development of an alternative cesium ion exchange resin to minimize the risk from reliance on a single product, implementing advanced analytical techniques to improve laboratory performance, adopting a thinner walled high level waste (HLW) canister to reduce waste volume and mission duration, and commissioning a comprehensive external flowsheet review of the design, along with its underpinning technologies, and projected plant operability. These challenges make it clear that WTP is a work in progress, but the challenges are being successfully resolved as the design and construction move on to completion. (authors)
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Directory of Open Access Journals (Sweden)
Porto Leonardo BO
2009-06-01
Full Text Available Abstract We present the case of a patient who sustained a penetrating injury to the chest caused by an attenuated energy rubber bullet and review the literature on thoracic injuries caused by plastic and rubber "less-lethal" munitions. The patient of this report underwent a right thoracotomy to extract the projectile as well as a wedge resection of the injured lung parenchyma. This case demonstrates that even supposedly safe riot control munition fired at close range, at the torso, can provoke serious injury. Therefore a thorough investigation and close clinical supervision are justified.
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International Nuclear Information System (INIS)
Columbo, P.; Fuhrmann, M.; Neilson, R.M. Jr; Sailor, V.L.
1982-11-01
The United States ocean dumping regulations developed pursuant to PL92-532, the Marine Protection, Research, and Sanctuaries Act of 1972, as amended, provide for a general policy of isolation and containment of low-level radioactive waste after disposal into the ocean. In order to determine whether any particular waste packaging system is adequate to meet this general requirement, it is necessary to establish a set of performance criteria against which to evaluate a particular packaging system. These performance criteria must present requirements for the behavior of the waste in combination with its immobilization agent and outer container in a deepsea environment. This report presents a working set of waste package performance criteria, and includes a glossary of terms, characteristics of low-level radioactive waste, radioisotopes of importance in low-level radioactive waste, and a summary of domestic and international regulations which control the ocean disposal of these wastes
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Assessment of work-related accidents associated with waste handling in Belo Horizonte (Brazil).
Mol, Marcos Pg; Pereira, Amanda F; Greco, Dirceu B; Cairncross, Sandy; Heller, Leo
2017-10-01
As more urban solid waste is generated, managing it becomes ever more challenging and the potential impacts on the environment and human health also become greater. Handling waste - including collection, treatment and final disposal - entails risks of work accidents. This article assesses the perception of waste management workers regarding work-related accidents in domestic and health service contexts in Belo Horizonte, Brazil. These perceptions are compared with national data from the Ministry of Social Security on accidents involving workers in solid waste management. A high proportion of accidents involves cuts and puncture injuries; 53.9% among workers exposed to domestic waste and 75% among those exposed to health service waste. Muscular lesions and fractures accounted for 25.7% and 12.5% of accidents, respectively. Data from the Ministry of Social Security diverge from the local survey results, presumably owing to under-reporting, which is frequent in this sector. Greater commitment is needed from managers and supervisory entities to ensure that effective measures are taken to protect workers' health and quality of life. Moreover, workers should defend their right to demand an accurate registry of accidents to complement monitoring performed by health professionals trained in risk identification. This would contribute to the improved recovery of injured workers and would require managers in waste management to prepare effective preventive action.
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Bioassay-based risk assessment of hazardous waste
Energy Technology Data Exchange (ETDEWEB)
Donnelly, K.C.; Brown, K.W.; He, L.Y. [Texas A and M Univ., College Station, TX (United States)
1994-12-31
Microbial bioassays have been used to assess the genotoxic hazard at more than 30 different hazardous waste sites. Environmental samples were extracted with dichloromethane and methanol, and the resulting residue tested using GC/MS analysis as well as the Salmonella Microsomal and E. coli Prophage Induction assays. At a munitions wastewater contaminated site, there was no correlation between mutagenicity in bacteria, and the risk as estimated from chemical analysis data of trinitrotoluene. Samples 202 and 204 from a coal gasification site contained 72 mg/kg and 9 mg/kg benzo(a)pyrene, whereas the mutagenic responses of these samples were 231 net revertants/mg and 902 revertants/mg, respectively. The data suggest that microbial bioassays provide a valuable tool for monitoring the interactions of the components of a complex mixture.
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Yu, Ann T W; Poon, C S; Wong, Agnes; Yip, Robin; Jaillon, Lara
2013-01-01
Waste management in the building industry in Hong Kong has become an important environmental issue. Particularly, an increasing amount of construction and demolition (C&D) waste is being disposed at landfill sites. In order to reduce waste generation and encourage reuse and recycling, the Hong Kong Government has implemented the Construction Waste Disposal Charging Scheme (CWDCS) to levy charges on C&D waste disposal to landfills. In order to provide information on the changes in reducing waste generation practice among construction participants in various work trades, a study was conducted after 3 years of implementation of the CWDCS via a structured questionnaire survey in the building industry in Hong Kong. The study result has revealed changes with work flows of the major trades as well as differentiating the levels of waste reduced. Three building projects in the public and private sectors were selected as case studies to demonstrate the changes in work flows and the reduction of waste achieved. The research findings reveal that a significant reduction of construction waste was achieved at the first 3 years (2006-2008) of CWDCS implementation. However, the reduction cannot be sustained. The major trades have been influenced to a certain extent by the implementation of the CWDCS. Slight improvement in waste management practices was observed, but reduction of construction waste in the wet-finishing and dry-finishing trades has undergone little improvement. Implementation of the CWDCS has not yet motivated subcontractors to change their methods of construction so as to reduce C&D waste. Copyright © 2012 Elsevier Ltd. All rights reserved.
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The health hazards of depleted uranium munitions. Part 1
International Nuclear Information System (INIS)
2001-01-01
Depleted uranium is a toxic and weakly radioactive metal used for a variety of purposes. Perhaps its most controversial use is in battlefield munitions, where it can be widely dispersed in the form of fine particles and shrapnel that may enter the bodies of combatants and others through inhalation, ingestion or wounding. It is a matter of legitimate public concern whether the use of this material in this way could create unacceptable health hazards or damage to the environment. The objective of our study has been to provide the best scientific understanding of the ways in which the material may be distributed, how it may be taken up by humans, and the potential implications for health. For politicians, any hazards to health have to be balanced against the military advantages that the use of these munitions confers. We have not tried to reach a judgment on these political issues, but we believe that a better scientific understanding of the extent of the hazards will make it easier for these wider questions to be addressed in a more objective way. This report is the first of two, and addresses the likely levels of exposure to depleted uranium, the resulting radiological risks, and the lessons to be learned from epidemiological studies. Our second report will address toxicological risks and environmental issues. So far, we conclude that risks from radiation are low for most soldiers on the battlefield, and for civilians who later return to the area. However, there are uncertainties about the maximal levels of exposure to depleted uranium on the battlefield, and there may be circumstances in which a few soldiers are exposed to levels of depleted uranium that result in a significant risk to health. Further studies are needed to determine the levels of exposure to depleted uranium that might occur on the battlefield and to judge whether such higher risks are likely to occur in practice
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International Nuclear Information System (INIS)
Yu, Ann T.W.; Poon, C.S.; Wong, Agnes; Yip, Robin; Jaillon, Lara
2013-01-01
Highlights: ► A significant reduction of construction waste was achieved at the first 3 years of CWDCS implementation. ► However, the reduction cannot be sustained. ► Implementation of the CWDCS has generated positive effects in waste reduction by all main trades. - Abstract: Waste management in the building industry in Hong Kong has become an important environmental issue. Particularly, an increasing amount of construction and demolition (C and D) waste is being disposed at landfill sites. In order to reduce waste generation and encourage reuse and recycling, the Hong Kong Government has implemented the Construction Waste Disposal Charging Scheme (CWDCS) to levy charges on C and D waste disposal to landfills. In order to provide information on the changes in reducing waste generation practice among construction participants in various work trades, a study was conducted after 3 years of implementation of the CWDCS via a structured questionnaire survey in the building industry in Hong Kong. The study result has revealed changes with work flows of the major trades as well as differentiating the levels of waste reduced. Three building projects in the public and private sectors were selected as case studies to demonstrate the changes in work flows and the reduction of waste achieved. The research findings reveal that a significant reduction of construction waste was achieved at the first 3 years (2006–2008) of CWDCS implementation. However, the reduction cannot be sustained. The major trades have been influenced to a certain extent by the implementation of the CWDCS. Slight improvement in waste management practices was observed, but reduction of construction waste in the wet-finishing and dry-finishing trades has undergone little improvement. Implementation of the CWDCS has not yet motivated subcontractors to change their methods of construction so as to reduce C and D waste.
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Energy Technology Data Exchange (ETDEWEB)
Yu, Ann T.W., E-mail: bsannyu@polyu.edu.hk [Department of Building and Real Estate, The Hong Kong Polytechnic University, Hung Hom, Kowloon (Hong Kong); Poon, C.S.; Wong, Agnes; Yip, Robin; Jaillon, Lara [Department of Civil and Structural Engineering, Hong Kong Polytechnic University, Hung Hom, Kowloon (Hong Kong)
2013-01-15
Highlights: Black-Right-Pointing-Pointer A significant reduction of construction waste was achieved at the first 3 years of CWDCS implementation. Black-Right-Pointing-Pointer However, the reduction cannot be sustained. Black-Right-Pointing-Pointer Implementation of the CWDCS has generated positive effects in waste reduction by all main trades. - Abstract: Waste management in the building industry in Hong Kong has become an important environmental issue. Particularly, an increasing amount of construction and demolition (C and D) waste is being disposed at landfill sites. In order to reduce waste generation and encourage reuse and recycling, the Hong Kong Government has implemented the Construction Waste Disposal Charging Scheme (CWDCS) to levy charges on C and D waste disposal to landfills. In order to provide information on the changes in reducing waste generation practice among construction participants in various work trades, a study was conducted after 3 years of implementation of the CWDCS via a structured questionnaire survey in the building industry in Hong Kong. The study result has revealed changes with work flows of the major trades as well as differentiating the levels of waste reduced. Three building projects in the public and private sectors were selected as case studies to demonstrate the changes in work flows and the reduction of waste achieved. The research findings reveal that a significant reduction of construction waste was achieved at the first 3 years (2006-2008) of CWDCS implementation. However, the reduction cannot be sustained. The major trades have been influenced to a certain extent by the implementation of the CWDCS. Slight improvement in waste management practices was observed, but reduction of construction waste in the wet-finishing and dry-finishing trades has undergone little improvement. Implementation of the CWDCS has not yet motivated subcontractors to change their methods of construction so as to reduce C and D waste.
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International Nuclear Information System (INIS)
Conley, T.B.; Morris, M.I.; Osborne-Lee, I.W.
1998-03-01
In May 1996, the US Department of Energy (DOE) Mixed Waste Focus Area (MWFA) initiated the Mercury Working Group (HgWG). The HgWG was established to address and resolve the issues associated with mercury contaminated mixed wastes. During the MWFA's initial technical baseline development process, three of the top four technology deficiencies identified were related to the need for amalgamation, stabilization, and separation removal technologies for the treatment of mercury and mercury contaminated mixed waste. The HgWG is assisting the MWFA in soliciting, identifying, initiating, and managing efforts to address these areas. The focus of the HgWG is to better establish the mercury related treatment technologies at the DOE sites, refine the MWFA technical baseline as it relates to mercury treatment, and make recommendations to the MWFA on how to most effectively address these needs. Based on the scope and magnitude of the mercury mixed waste problem, as defined by HgWG, solicitations and contract awards have been made to the private sector to demonstrate both the amalgamation and stabilization processes using actual mixed wastes. Development efforts are currently being funded that will address DOE's needs for separation removal processes. This paper discusses the technology selection process, development activities, and the accomplishments of the HgWG to date through these various activities
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International Nuclear Information System (INIS)
Ayame, Y.; Tanabe, T.; Takahashi, K.; Takeda, S.
2001-07-01
This investigation was conducted as a part of planning the low-level radioactive waste management program (LLW management program). The aim of this investigation was contributed to compile the radioactive waste database of JNC's LLW management program. All nuclear facilities of the Tokai works and Ningyo-toge Environmental Engineering Center were investigated in this work. The wastes generated by the decommissioning of each nuclear facility were classified into radioactive waste and others (exempt waste and non-radioactive waste), and the amount of the wastes was estimated. The estimated amounts of radioactive wastes generated by decommissioning of the nuclear facilities are as follows. (1) Tokai works: The amount of waste generated by decommissioning of nuclear facilities of the Tokai works is about 1,079,100 ton. The amount of radioactive waste is about 15,400 ton. The amount of exempt waste and non-radioactive waste is about 1,063,700 ton. (2) Ningyo-toge Environmental Engineering Center: The amount of waste generated by decommissioning of nuclear facilities of Ningyo-toge Environmental Engineering Center is about 112,500 ton. The amount of radioactive waste is about 7,800 ton. The amount of exempt waste and non-radioactive waste is about 104,700 ton. (author)
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Bioinspired polarization navigation sensor for autonomous munitions systems
Giakos, G. C.; Quang, T.; Farrahi, T.; Deshpande, A.; Narayan, C.; Shrestha, S.; Li, Y.; Agarwal, M.
2013-05-01
Small unmanned aerial vehicles UAVs (SUAVs), micro air vehicles (MAVs), Automated Target Recognition (ATR), and munitions guidance, require extreme operational agility and robustness which can be partially offset by efficient bioinspired imaging sensor designs capable to provide enhanced guidance, navigation and control capabilities (GNC). Bioinspired-based imaging technology can be proved useful either for long-distance surveillance of targets in a cluttered environment, or at close distances limited by space surroundings and obstructions. The purpose of this study is to explore the phenomenology of image formation by different insect eye architectures, which would directly benefit the areas of defense and security, on the following four distinct areas: a) fabrication of the bioinspired sensor b) optical architecture, c) topology, and d) artificial intelligence. The outcome of this study indicates that bioinspired imaging can impact the areas of defense and security significantly by dedicated designs fitting into different combat scenarios and applications.
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National Research Council Canada - National Science Library
D'Agostino, Davi M
2007-01-01
The Government Accountability Office (GAO) is releasing a report today on lessons learned concerning the need for security over conventional munitions storage sites that provides the basis for this testimony...
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International Nuclear Information System (INIS)
Yui, Mikazu; Ishikawa, Hirohisa; Umeki, Hiroyuki; Hioki, Kazumasa; Naito, Morimasa; Makino, Hitoshi; Oda, Chie; Tachi, Yukio; Mitsui, Seiichiro; Shibata, Masahiro; Watanabe, Atsuo; Yoshino, Kyoji; Seo, Toshihiro; Miyamoto, Yoichi; Nutt, Mark; Peters, Mark; Bresee, James; Lesica, Sue; Schwab, Patrick; Gomberg, Steve; Jones, Jay; Halsey, Bill; Marra, John; Vienna, John; Gombert, Drik; McMahon, Kevin; James, Scott; Caporuscio, Florie
2010-05-01
The activity of Phase I of the Waste Management Working Group under the United States - Japan Joint Nuclear Energy Action Plan started in 2007. The US-Japan JNEAP is a bilateral collaborative framework to support the global implementation of safe, secure, and sustainable, nuclear fuel cycles (referred to in this document as fuel cycles). The Waste Management Working Group was established by strong interest of both parties, which arise from the recognition that development and optimization of waste management and disposal system(s) are central issues of the present and future nuclear fuel cycles. This report summarizes the activity of the Waste Management Working Group that focused on consolidation of the existing technical basis between the U.S. and Japan and the joint development of a plan for future collaborative activities. Firstly, the political/regulatory frameworks related to nuclear fuel cycles in both countries were reviewed. The various advanced fuel cycle scenarios that have been considered in both countries were then surveyed and summarized. The working group established the working reference scenario for the future cooperative activity that corresponds to a fuel cycle scenario being considered both in Japan and the U.S. This working scenario involves transitioning from a once-through fuel cycle utilizing light water reactors to a one-pass uranium-plutonium fuel recycle in light water reactors to a combination of light water reactors and fast reactors with plutonium, uranium, and minor actinide recycle, ultimately concluding with multiple recycle passes primarily using fast reactors. Considering the scenario, current and future expected waste streams, treatment and inventory were discussed, and the relevant information was summarized. Second, the waste management/disposal system optimization was discussed. Repository system concepts were reviewed, repository design concepts for the various classifications of nuclear waste were summarized, and the factors
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Methods of sampling airborne fungi in working environments of waste treatment facilities.
Černá, Kristýna; Wittlingerová, Zdeňka; Zimová, Magdaléna; Janovský, Zdeněk
2016-01-01
The objective of the present study was to evaluate and compare the efficiency of a filter based sampling method and a high volume sampling method for sampling airborne culturable fungi present in waste sorting facilities. Membrane filters method was compared with surface air system method. The selected sampling methods were modified and tested in 2 plastic waste sorting facilities. The total number of colony-forming units (CFU)/m3 of airborne fungi was dependent on the type of sampling device, on the time of sampling, which was carried out every hour from the beginning of the work shift, and on the type of cultivation medium (p airborne fungi ranged 2×102-1.7×106 CFU/m3 when using the membrane filters (MF) method, and 3×102-6.4×104 CFU/m3 when using the surface air system (SAS) method. Both methods showed comparable sensitivity to the fluctuations of the concentrations of airborne fungi during the work shifts. The SAS method is adequate for a fast indicative determination of concentration of airborne fungi. The MF method is suitable for thorough assessment of working environment contamination by airborne fungi. Therefore we recommend the MF method for the implementation of a uniform standard methodology of airborne fungi sampling in working environments of waste treatment facilities. This work is available in Open Access model and licensed under a CC BY-NC 3.0 PL license.
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Exposing government response action contractors to environmental tort liability
International Nuclear Information System (INIS)
Roy, M.J.
1991-01-01
Government contractors, particularly those involved with hazardous waste response action activities, are encountering increased risks for environmental tort liabilities. Contracts often include tasks and work assignments requiring the management of industrial, chemical, nuclear or mining wastes, spent fuels, munitions or other toxic substances. Contractors exposure to liability for damages results directly from the environmental laws and regulations pursuant to which the Government has contracted them to respond. Additionally, contractors may be exposed to common law liability under such dogmas as nuisance, trespass and strict liability in tort
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The role and the results of the European Community's R and D work on radioactive waste management
International Nuclear Information System (INIS)
Orlowski, S.; Girardi, F.
1986-01-01
The role and results of the European Community's research and development (R and D) work on radioactive waste management are described. The R and D work includes: radioactive waste conditioning, characterization and storage, materials science studies for the storage, geological media confinement studies, and radionuclide migration investigations. Financial management and the long term, and the socio-political aspects of waste management, are also discussed. (U.K.)
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Regional cooperation-activities of the working group on waste management
International Nuclear Information System (INIS)
Brooks, G.L.
1987-01-01
A Working Group on Waste Management was formally established by the Pacific Basin Nuclear Cooperation Committee at its meeting on November 19, 1986. Co-chairmen are Dr. Kunihiko Uematsu of Japan and the author, Gordon L. Brooks of Canada. Since the Working Group is newly formed, a consensus program has not yet been developed. In lieu of this, the author suggests a series of basic issues and possible areas of future collaboration which could serve as a starting point for the Working Group in developing an appropriate cooperative program. (author)
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Influence of working fluids on Organic Rankine Cycle for waste heat recovery applications
Energy Technology Data Exchange (ETDEWEB)
Struzyna, Ralf; Eifler, Wolfgang; Steinmill, Jens [Bochum Univ. (Germany). Lehrstuhl fuer Verbrennungsmotoren
2012-11-01
More than 50% of the energy contained in fuel is lost due to the loss of heat content to the exhaust gas, the cooling water or the charge air cooler medium. Therefore, one of the most promising attempts to further increase the efficiency of internal combustion engines is waste heat recovery by means of a combined process. The Organic Rankine Cycle (ORC) is a promising process for waste heat recovery systems. The main purpose is to identify suitable working fluids to achieve best system performance. Therefore an analysis of the influence of different working fluids on system output is required. (orig.)
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Modelling the work flow of a nuclear waste management program
Energy Technology Data Exchange (ETDEWEB)
Hoeyer Mortensen, K. [Aarhus Univ., Computer Science Dept. (Denmark); Pinci, V. [Meta Software Corporation, Cambridge, MA (United States)
1997-03-01
In this paper we describe a modelling project to improve a nuclear waste management program in charge of the creation of a new system for the permanent disposal of nuclear waste. SADT (Structural Analysis and Design Technique) is used in order to provide a work-flow description of the functions to be performed by the waste management program. This description is then translated into a number of Coloured Petri Nets (CPN or CP-nets) corresponding to different program functions where additional behavioural inscriptions provide basis for simulation. Each of these CP-nets is simulated to produce timed event charts that are useful for understanding the behaviour of the program functions under different scenarios. Then all the CPN models are linked together to form a single stand-alone application that is useful for validating the interaction and cooperation between the different program functions. A technique for linking executable CPN models is developed for supporting large modelling projects and parallel development of independent CPN models. (au) 11 refs.
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Modelling the work flow of a nuclear waste management program
International Nuclear Information System (INIS)
Hoeyer Mortensen, K.; Pinci, V.
1997-03-01
In this paper we describe a modelling project to improve a nuclear waste management program in charge of the creation of a new system for the permanent disposal of nuclear waste. SADT (Structural Analysis and Design Technique) is used in order to provide a work-flow description of the functions to be performed by the waste management program. This description is then translated into a number of Coloured Petri Nets (CPN or CP-nets) corresponding to different program functions where additional behavioural inscriptions provide basis for simulation. Each of these CP-nets is simulated to produce timed event charts that are useful for understanding the behaviour of the program functions under different scenarios. Then all the CPN models are linked together to form a single stand-alone application that is useful for validating the interaction and cooperation between the different program functions. A technique for linking executable CPN models is developed for supporting large modelling projects and parallel development of independent CPN models. (au) 11 refs
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Photochemical transformation of the insensitive munitions compound 2,4-dinitroanisole
Energy Technology Data Exchange (ETDEWEB)
Rao, Balaji, E-mail: anandharaob@ornl.gov [Environmental Sciences Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States); Wang, Wei [Environmental Sciences Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States); Cai, Qingsong; Anderson, Todd [Department of Environmental Toxicology, The Institute of Environment and Human Health, Texas Tech University, Lubbock, TX (United States); Gu, Baohua, E-mail: gub1@ornl.gov [Environmental Sciences Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)
2013-01-15
The insensitive munitions compound 2,4-dinitroanisole (DNAN) is increasingly being used as a replacement for traditional, sensitive munitions compounds (e.g., trinitrotoluene [TNT]), but the environmental fate and photo-transformation of DNAN in natural water systems are currently unknown. In this study, we investigated the photo-transformation rates of DNAN with both ultraviolet (UV) and sunlight irradiation under different environmentally relevant conditions. Sunlight photo-transformation of DNAN in water was found to follow predominantly pseudo-first-order decay kinetics with an average half-life (t{sub 1/2}) of approximately 0.70 d and activation energy (E{sub a}) of 53 kJ mol{sup −1}. Photo-transformation rates of DNAN were dependent on the wavelength of the light source: irradiation with UV-B light (280–315 nm) resulted in a greater quantum yield of transformation (ϕ{sub UV-B} = 3.7 × 10{sup −4}) than rates obtained with UV-A light (ϕ{sub UV-A} = 2.9 × 10{sup −4} at 316–400 nm) and sunlight (ϕ{sub sun} = 1.1 × 10{sup −4}). Photo-oxidation was the dominant mechanism for DNAN photo-transformation, based on the formation of nitrite (NO{sub 2}{sup −}) and nitrate (NO{sub 3}{sup −}) as major N species and 2,4-dinitrophenol as the minor species. Environmental factors (e.g., temperature, pH, and the presence or absence of naturally dissolved organic matter) displayed modest to little effects on the rate of DNAN photo-transformation. These observations indicate that sunlight-induced photo-transformation of DNAN may represent a significant abiotic degradation pathway in surface water, which may have important implications in evaluating the potential impacts and risks of DNAN in the environment. - Highlights: ► DNAN photo-transformation kinetics was dependent on light source and temperature. ► Photolysis produced harmful by-products that included dinitrophenol and nitrate. ► Photo-oxidation was determined to be the likely pathway of DNAN
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2010-07-01
... mixing zone should be considered as a place where wastes and water mix and not as a place where effluents... spoil, solid waste, incinerator residue, sewage, garbage, sewage sludge, munitions, chemical wastes... equipment, rock, sand, cellar dirt, and industrial, municipal, and agricultural waste discharged into water...
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Arabidopsis thaliana root transcriptome responses to the munition, hexahydro-1,3,5-trinitro-1,3,5-triazine (RDX), were assessed using serial analysis of gene expression (SAGE). Comparison of the transcriptional profile for the RDX response to a profile previously described for Ar...
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Friedel, M. J.; Asch, T. H.; Oden, C.
2012-08-01
The remediation of land containing munitions and explosives of concern, otherwise known as unexploded ordnance, is an ongoing problem facing the U.S. Department of Defense and similar agencies worldwide that have used or are transferring training ranges or munitions disposal areas to civilian control. The expense associated with cleanup of land previously used for military training and war provides impetus for research towards enhanced discrimination of buried unexploded ordnance. Towards reducing that expense, a multiaxis electromagnetic induction data collection and software system, called ALLTEM, was designed and tested with support from the U.S. Department of Defense Environmental Security Technology Certification Program. ALLTEM is an on-time time-domain system that uses a continuous triangle-wave excitation to measure the target-step response rather than traditional impulse response. The system cycles through three orthogonal transmitting loops and records a total of 19 different transmitting and receiving loop combinations with a nominal spatial data sampling interval of 20 cm. Recorded data are pre-processed and then used in a hybrid discrimination scheme involving both data-driven and numerical classification techniques. The data-driven classification scheme is accomplished in three steps. First, field observations are used to train a type of unsupervised artificial neural network, a self-organizing map (SOM). Second, the SOM is used to simultaneously estimate target parameters (depth, azimuth, inclination, item type and weight) by iterative minimization of the topographic error vectors. Third, the target classification is accomplished by evaluating histograms of the estimated parameters. The numerical classification scheme is also accomplished in three steps. First, the Biot-Savart law is used to model the primary magnetic fields from the transmitter coils and the secondary magnetic fields generated by currents induced in the target materials in the
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Friedel, M.J.; Asch, T.H.; Oden, C.
2012-01-01
The remediation of land containing munitions and explosives of concern, otherwise known as unexploded ordnance, is an ongoing problem facing the U.S. Department of Defense and similar agencies worldwide that have used or are transferring training ranges or munitions disposal areas to civilian control. The expense associated with cleanup of land previously used for military training and war provides impetus for research towards enhanced discrimination of buried unexploded ordnance. Towards reducing that expense, a multiaxis electromagnetic induction data collection and software system, called ALLTEM, was designed and tested with support from the U.S. Department of Defense Environmental Security Technology Certification Program. ALLTEM is an on-time time-domain system that uses a continuous triangle-wave excitation to measure the target-step response rather than traditional impulse response. The system cycles through three orthogonal transmitting loops and records a total of 19 different transmitting and receiving loop combinations with a nominal spatial data sampling interval of 20 cm. Recorded data are pre-processed and then used in a hybrid discrimination scheme involving both data-driven and numerical classification techniques. The data-driven classification scheme is accomplished in three steps. First, field observations are used to train a type of unsupervised artificial neural network, a self-organizing map (SOM). Second, the SOM is used to simultaneously estimate target parameters (depth, azimuth, inclination, item type and weight) by iterative minimization of the topographic error vectors. Third, the target classification is accomplished by evaluating histograms of the estimated parameters. The numerical classification scheme is also accomplished in three steps. First, the Biot–Savart law is used to model the primary magnetic fields from the transmitter coils and the secondary magnetic fields generated by currents induced in the target materials in the
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A Biography of the Trousered Munitions Women’s Uniform of World War 1
Roberts, Jennifer
2017-01-01
Ce chapitre fournit une vue d’ensemble de la recherche pour un exemple survivant de l’uniforme de pantalons des « munitionettes », alors que les travailleurs dans les usines de munitions dans la Première Guerre Mondiale étaient reconnus. Si nous examinons la réaction sur les femmes qui portent un vêtement d’homme et les discussions d’émancipation de cet uniforme, ces recherches ont étudié considérablement les archives jadis moins utilisées dans l’histoire des vêtements. Comme il n’existe plus...
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Removal of the liquid waste storage tank LV-2 in JRTF. Part 2. Removal works
International Nuclear Information System (INIS)
Kanayama, Fumihiko; Hagiya, Kazuaki; Sunaoshi, Mizuho; Muraguchi, Yoshinori; Satomi, Shinichi; Nemoto, Kouichi; Terunuma, Akihiro; Shiraishi, Kunio; Ito, Shinichi
2011-06-01
Dismantling activities of components in JAERI's Reprocessing Test Facility (JRTF) started from 1996 as a part of decommissioning of this facility. Removing out of a large liquid waste storage tank LV-2 as a whole tank from the annex building B without cutting in pieces to confirm safety and efficiency of this method started from 2006. After preparatory works, ceiling of LV-2 room was opened, and LV-2 was transferred. Useful data such as manpower, radiation control and waste amount through these works were collected, and work efficiency was analyzed by using of these data. (author)
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International Nuclear Information System (INIS)
Rackham, Jamie; Weber, Anne-Laure; Chard, Patrick
2012-01-01
The first evaluation of NDA performance values was undertaken by the ESARDA Working Group for Standards and Non Destructive Assay Techniques and was published in 1993. Almost ten years later in 2002 the Working Group reviewed those values and reported on improvements in performance values and new measurement techniques that had emerged since the original assessment. The 2002 evaluation of NDA performance values did not include waste measurements (although these had been incorporated into the 1993 exercise), because although the same measurement techniques are generally applied, the performance is significantly different compared to the assay of conventional Safeguarded special nuclear material. It was therefore considered more appropriate to perform a separate evaluation of performance values for waste assay. Waste assay is becoming increasingly important within the Safeguards community, particularly since the implementation of the Additional Protocol, which calls for declaration of plutonium and HEU bearing waste in addition to information on existing declared material or facilities. Improvements in the measurement performance in recent years, in particular the accuracy, mean that special nuclear materials can now be accounted for in wastes with greater certainty. This paper presents an evaluation of performance values for the NDA techniques in common usage for the assay of waste containing special nuclear material. The main topics covered by the document are: 1- Techniques for plutonium bearing solid wastes 2- Techniques for uranium bearing solid wastes 3 - Techniques for assay of fissile material in spent fuel wastes. Originally it was intended to include performance values for measurements of uranium and plutonium in liquid wastes; however, as no performance data for liquid waste measurements was obtained it was decided to exclude liquid wastes from this report. This issue of the performance values for waste assay has been evaluated and discussed by the ESARDA
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Energy Technology Data Exchange (ETDEWEB)
Rackham, Jamie [Babcock International Group, Sellafield, Seascale, Cumbria, (United Kingdom); Weber, Anne-Laure [Institut de Radioprotection et de Surete Nucleaire Fontenay-Aux-Roses (France); Chard, Patrick [Canberra, Forss Business and Technology park, Thurso, Caithness (United Kingdom)
2012-12-15
The first evaluation of NDA performance values was undertaken by the ESARDA Working Group for Standards and Non Destructive Assay Techniques and was published in 1993. Almost ten years later in 2002 the Working Group reviewed those values and reported on improvements in performance values and new measurement techniques that had emerged since the original assessment. The 2002 evaluation of NDA performance values did not include waste measurements (although these had been incorporated into the 1993 exercise), because although the same measurement techniques are generally applied, the performance is significantly different compared to the assay of conventional Safeguarded special nuclear material. It was therefore considered more appropriate to perform a separate evaluation of performance values for waste assay. Waste assay is becoming increasingly important within the Safeguards community, particularly since the implementation of the Additional Protocol, which calls for declaration of plutonium and HEU bearing waste in addition to information on existing declared material or facilities. Improvements in the measurement performance in recent years, in particular the accuracy, mean that special nuclear materials can now be accounted for in wastes with greater certainty. This paper presents an evaluation of performance values for the NDA techniques in common usage for the assay of waste containing special nuclear material. The main topics covered by the document are: 1- Techniques for plutonium bearing solid wastes 2- Techniques for uranium bearing solid wastes 3 - Techniques for assay of fissile material in spent fuel wastes. Originally it was intended to include performance values for measurements of uranium and plutonium in liquid wastes; however, as no performance data for liquid waste measurements was obtained it was decided to exclude liquid wastes from this report. This issue of the performance values for waste assay has been evaluated and discussed by the ESARDA
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40 CFR 401.11 - General definitions.
2010-07-01
..., incinerator residue, sewage, garbage, sewage sludge, munitions, chemical wastes, biological materials... and agricultural waste discharged into water. It does not mean (1) sewage from vessels or (2) water... established by best engineering practice. (q) The term process waste water means any water which, during...
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WIPP Facility Work Plan for Solid Waste Management Units and Areas of Concern
International Nuclear Information System (INIS)
2001-01-01
This 2001 Facility Work Plan (FWP) has been prepared as required by Module VII, Section VII.M.1 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit); (NMED, 1999a), and incorporates comments from the New Mexico Environment Department (NMED) received on December 6, 2000 (NMED, 2000a). This February 2001 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) specified in the Permit. The permittees are evaluating data from previous investigations of the SWMUs and AOCs against the newest guidance proposed by the NMED. Based on these data, the permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a Facility to exit the schedule of compliance contained in the Facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA process can be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable alternative to the RFI Work Plan specified in the Permit.
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Study of working fluid selection of organic Rankine cycle (ORC) for engine waste heat recovery
International Nuclear Information System (INIS)
Wang, E.H.; Zhang, H.G.; Fan, B.Y.; Ouyang, M.G.; Zhao, Y.; Mu, Q.H.
2011-01-01
Organic Rankine Cycle (ORC) could be used to recover low-grade waste heat. When a vehicle is running, the engine exhaust gas states have a wide range of variance. Defining the operational conditions of the ORC that achieve the maximum utilization of waste heat is important. In this paper the performance of different working fluids operating in specific regions was analyzed using a thermodynamic model built in Matlab together with REFPROP. Nine different pure organic working fluids were selected according to their physical and chemical properties. The results were compared in the regions when net power outputs were fixed at 10 kW. Safety levels and environmental impacts were also evaluated. The outcomes indicate that R11, R141b, R113 and R123 manifest slightly higher thermodynamic performances than the others; however, R245fa and R245ca are the most environment-friendly working fluids for engine waste heat-recovery applications. The optimal control principle of ORC under the transient process is discussed based on the analytical results. -- Highlights: → R11, R141b, R113 and R123 manifest the best thermodynamic performances. → R245fa and R245ca are the most environment-friendly working fluids for the engine waste heat-recovery application. → The condensing temperature has more important effect than the evaporating pressure to the performance of ORC. → The optimal control principle of ORC under the transient process was defined according to the calculation results for the vehicle engine waste heat-recovery application. → ORC thermodynamic model was built in Matlab together with REFPROP.
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International Nuclear Information System (INIS)
2015-01-01
PNGMDR is the French national plan for the management of radioactive materials and wastes. After a discussion of the stakes associated with the optimisation of the different sectors involved in radioactive waste management (production, sorting, processing, packaging, warehousing, storage), this reports proposes a description of wastes for which a sector optimisation study has been performed (graphite wastes, Marcoule bitumen packages, common solid residues, cemented solid wastes in concrete containers from Areva La Hague), describes the various studies optimisation ways and alternate scenarios for these different wastes. It analyses and discusses the progress status of the studies optimisation ways: improvement of the characterisation of graphite and bituminous wastes, studies and works on the storage of low-level-long-lived wastes, studies on the processing of graphite wastes, of bituminous packages and common solid residues. Other issues are evoked: the case of wastes produced by dismantling operations, and a technical-economic approach. Perspectives and future works are discussed for the different considered wastes
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Jakacki, Jaromir; Golenko, Mariya
2014-05-01
Two hydrodynamical models (Princeton Ocean Model (POM) and Parallel Ocean Program (POP)) have been implemented for the Baltic Sea area that consists of locations of the dumped chemical munitions during II War World. The models have been configured based on similar data source - bathymetry, initial conditions and external forces were implemented based on identical data. The horizontal resolutions of the models are also very similar. Several simulations with different initial conditions have been done. Comparison and analysis of the bottom currents from both models have been performed. Based on it estimating of the dangerous area and critical time have been done. Also lagrangian particle tracking and passive tracer were implemented and based on these results probability of the appearing dangerous doses and its time evolution have been presented. This work has been performed in the frame of the MODUM project financially supported by NATO.
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International Nuclear Information System (INIS)
Biggs, Simon; Fairweather, Michael; Young, James; Grimes, Robin W.; Milestone, Neil; Livens, Francis
2009-01-01
The Keeping the Nuclear Option Open (KNOO) research consortium is a four-year research council funded initiative addressing the challenges related to increasing the safety, reliability and sustainability of nuclear power in the UK. Through collaboration between key industrial and governmental stakeholders, and with international partners, KNOO was established to maintain and develop skills relevant to nuclear power generation. Funded by a research grant of Pounds 6.1 M from the 'Towards a Sustainable Energy Economy Programme' of the UK Research Councils, it represents the single largest university-based nuclear research programme in the UK for more than 30 years. The programme is led by Imperial College London, in collaboration with the universities of Manchester, Sheffield, Leeds, Bristol, Cardiff and the Open University. These universities are working with the UK nuclear industry, who contributed a further Pounds 0.4 M in funding. The industry/government stakeholders include AWE, British Energy, the Department for Environment, Food and Rural Affairs, the Environment Agency, the Health and Safety Executive, Doosan Babcock, the Ministry of Defence, Nirex, AMEC NNC, Rolls-Royce PLC and the UK Atomic Energy Authority. Work Package 3 of this consortium, led by the University of Leeds, concerns 'An Integrated Approach to Waste Immobilisation and Management', and involves Imperial College London, and the Universities of Manchester and Sheffield. The aims of this work package are: to study the re-mobilisation, transport, solid-liquid separation and immobilisation of particulate wastes; to develop predictive models for particle behaviour based on atomic scale, thermodynamic and process scale simulations; to develop a fundamental understanding of selective adsorption of nuclides onto filter systems and their immobilisation; and to consider mechanisms of nuclide leaving and transport. The paper describes highlights from this work in the key areas of multi-scale modeling
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Analysis of abandoned potential CERCLA hazardous waste sites using historic aerial photographs
International Nuclear Information System (INIS)
Rosowitz, D.W.; Franzen, P.A.; Green, D.J.
1993-01-01
Aerial photographs of varying scale from federal agencies and commercial aerial service companies covering the years 1938, 1942, 1948, 1952, 1957, 1960, 1970, 1971, 1977, and 1986 of the Edgewood Area of Aberdeen Proving Ground (APG), Maryland, (Gunpowder Neck 7.5 Minute United States Geological Survey Topographic Quadrangle Map) were evaluated for identification of potential Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) hazardous waste sites and land use changes for approximately 1500 acres (610 hectares) used in the testing of military-related chemicals and munitions on Carroll Island and Graces Quarters. Detailed testing records exist only for July 1964 to December 1971, thus making the interpretation of aerial photographs a valuable tool in reconstructing past activities from the late 1930s to June 1964 and guiding future sampling locations in the multiphased CERCLA process. Many potential test sites were activated by either clear-cutting tracks of vegetation or using existing cleared land until final abandonment of the site(s) circa 1974-1975. Ground inspection of open-quotes land scarringclose quotes at either known or suspected sites was essential for verifying the existence, location, and subsequent sampling of potential CERCLA sites. Photomorphic mapping techniques are described to delineate and compare different land use changes in past chemical and munitions handling and testing. Delineation of features was based on photographic characteristics of tone, pattern, texture, shape, shadow, size, and proximity to known features. 7 refs., 9 figs
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Long term governance for radioactive waste management. Final report of Cowan2 - work package 4
International Nuclear Information System (INIS)
Schneider, Th.; Schieber, C.; Lavele, S.
2006-12-01
This report aims at identifying key features for the long term governance of radioactive waste. It is proposed by the COWAN2 Work Package 4 the purpose of which was to identify, discuss and analyse the institutional, ethical, economic and legal considerations raised by long term radioactive waste storage or disposal on the three interrelated issues of: responsibility and ownership of radioactive waste on the long term, continuity of local dialogue between stakeholders and monitoring of radioactive waste management facilities, and compensation and sustainable development. The aim is also to propose guidelines in order to better address long term issues in decision-making processes and start long term governance
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Long term governance for radioactive waste management. Final report of Cowan2 - work package 4
Energy Technology Data Exchange (ETDEWEB)
Schneider, Th.; Schieber, C.; Lavele, S.
2006-12-15
This report aims at identifying key features for the long term governance of radioactive waste. It is proposed by the COWAN2 Work Package 4 the purpose of which was to identify, discuss and analyse the institutional, ethical, economic and legal considerations raised by long term radioactive waste storage or disposal on the three interrelated issues of: responsibility and ownership of radioactive waste on the long term, continuity of local dialogue between stakeholders and monitoring of radioactive waste management facilities, and compensation and sustainable development. The aim is also to propose guidelines in order to better address long term issues in decision-making processes and start long term governance
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1976-07-01
and the neuromuscular effects in these dogs were not due to hypocalcemia . The lowest serum calcium concen- tration in these dogs was 4.2 meq/liter...motor end plate might produce a local hypocalcemia . Such a mechanism is purely speculative. Qualitatively and quantitavely, most of the effects of 2,6...I ýNw,- -MIM I/ MIDWEST RESEARCH INS14ITUTE H0q .3L I LU -_ MAMMALIAN TOXICITY OF MUNITIONS COMPOUlNDSPHASE II: EFFECTS OF MiULTIPLE DOSES C* •PART
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PNGMDR 2013-2015. 2015 report by the 'wastes presently without management pathway' work-group
International Nuclear Information System (INIS)
2014-01-01
PNGMDR is the French national plan for the management of radioactive materials and wastes. After having recalled the specific request made by the PNGMDR, the conclusion of the previous report, and presented the adopted methodology, this report proposes an inventory of wastes which had no management pathway at the end of 2012. Then, the authors propose an overview of the progress status of processes for the processing of priority waste families: asbestos-containing wastes, mercury and mercury wastes, organic oils and liquids. For each of these types, an inventory is given, and, should the occasion occur, envisaged processes, process development status, and perspectives are discussed. A last part proposes an overview of the progress of works on components activated by particle accelerators. An appendix indicates waste origins
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Solid waste programs Fiscal Year 1995 multi-year program plan/fiscal year work plan WBS 1.2.1
International Nuclear Information System (INIS)
McCarthy, M.M.
1994-09-01
The Hanford Mission Plan, Volume 1, Site Guidance identifies the need for the Solid Waste Program to treat, store, and dispose of a wide variety of solid material types consisting of multiple radioactive and hazardous waste classes. This includes future Hanford Site activities which will generate new wastes that must be handled as cleanup activities are completed. Solid wastes are typically categorized as transuranic waste, low level waste, low level mixed waste, and hazardous waste. To meet this need the Solid Waste Program has defined its mission as the following - receive, store, treat, decontaminate, and dispose of solid radioactive and nonradioactive dangerous wastes in a safe, cost effective and environmentally compliant manner. This workbook contains the program overview, program baselines and fiscal year work plan for the Solid Waste Program
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WIPP Facility Work Plan for Solid Waste Management Units and Areas of Concern
International Nuclear Information System (INIS)
2002-01-01
This 2002 Facility Work Plan (FWP) has been prepared as required by Module VII, Permit Condition VII.U.3 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit, NM4890139088-TSDF (the Permit) (New Mexico Environment Department [NMED], 1999a), and incorporates comments from the NMED received on December 6, 2000 (NMED, 2000a). This February 2002 FWP describes the programmatic facility-wide approach to future investigations at Solid Waste Management Units (SWMU) and Areas of Concern (AOC) specified in the Permit. The Permittees are evaluating data from previous investigations of the SWMUs and AOCs against the most recent guidance proposed by the NMED. Based on these data, and completion of the August 2001 sampling requested by the NMED, the Permittees expect that no further sampling will be required and that a request for No Further Action (NFA) at the SWMUs and AOCs will be submitted to the NMED. This FWP addresses the current Permit requirements. It uses the results of previous investigations performed at WIPP and expands the investigations as required by the Permit. As an alternative to the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) specified in Module VII of the Permit, current NMED guidance identifies an Accelerated Corrective Action Approach (ACAA) that may be used for any SWMU or AOC (NMED, 1998). This accelerated approach is used to replace the standard RFI Work Plan and Report sequence with a more flexible decision-making approach. The ACAA process allows a facility to exit the schedule of compliance contained in the facility's Hazardous and Solid Waste Amendments (HSWA) permit module and proceed on an accelerated time frame. Thus, the ACAA processcan be entered either before or after an RFI Work Plan. According to the NMED's guidance, a facility can prepare an RFI Work Plan or Sampling and Analysis Plan (SAP) for any SWMU or AOC (NMED, 1998). Based on this guidance, a SAP constitutes an acceptable
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Main directions of works on radioactive waste management at 30-km zone near the Chernobyl' NPP
International Nuclear Information System (INIS)
Grushinskij, B.Ya.; Komarov, V.I.; Proskuryakov, A.N.; Kham'yanov, L.N.; Khubizov, S.B.; Ignatenko, E.I.; Ryzhkova, V.N.; Luppov, V.A.; Matskevich, G.V.; Frolov, V.N.
1989-01-01
Main points and stages of creating an specialized enterprise for centralized reprocessing and radioactive waste disposal are considered. The enterprise is intended for collection conditioning and burial of all types of radioactive wastes, formed during liquidation of accident effect at the Chernobyl' NPP as well as forming in operation of NPP. The enterprise is also used to decontaminate equipment and constructions, for reprocessing of secondary radioactive wastes forming during decontamination process of equipment constructions, transport and work clothes
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International Nuclear Information System (INIS)
Soares, M.L.L.; Gomes, H.
1974-01-01
The work developed until 1974 by the group of IPR (Instituto de Pesquisas Radioativas - MG, Brazil) responsible for the treatment of radioative wastes, is presented. The evaporation of liquid effluents of medium level activity, the treatment of gaseous effluents, the vitrification of high level liquid wastes and the sites for the final disposal of wastes are discussed [pt
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International Nuclear Information System (INIS)
Schmitt, R.
1996-01-01
Many institutions have participated in public relations work concerning the final disposal of radioactive wastes in Germany since preliminary research work in this field was started in the early 1960's. The large number of institutions involved necessitates a uniform phraseology, kept up to date by permanent exchanges of information. The Press and Public Information Section of the Bundesamt fur Strahlenschutz (BfS) is responsible for co-ordination, with the aim of presenting both the general disposal concept of the Federal Government, and the work done within the scope of individual projects in the field of final waste disposal. Public relations activities are supported by the Deutsche Gesellschaft zum Bau and Betrieb von Endlagern fur Abfallstoffe mbH (DBE) which conducts public relations work at site level. Since the early sixties radioactive waste disposal policy in Germany has been based on the decision that all kinds of radioactive wastes should be disposed of in deep geological formations. One operating repository and two different disposal projects are currently under was in Germany. The paper discusses these three sites and their public relations efforts. A lot of work has been done in the public relations field in Germany, for more than 15 years now. Open, comprehensive information and reporting are essential for transparent and credible representations of the activities necessary for the disposal of radioactive waste, as well as to create a climate of confidence in order to fashion a position identity for such large-scale projects. In addition to personal contacts, target-group oriented information meetings and scientifically understandable information material are important means to achieved this end. The permanent presence of contact persons at the sites supports this objective, especially with regard to information directed towards the general public. (author)
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Coelho, Alexa Pupiara Flores; Beck, Carmem Lúcia Colomé; Silva, Rosângela Marion da; Prestes, Francine Cassol; Camponogara, Silviamar; Peserico, Anahlú
2017-04-01
describe elements that promote satisfaction and dissatisfaction in the work of recyclable solid waste segregators and conduct a nursing action focused on these elements. qualitative research, convergent-care, conducted with members of the cooperative. Data production occurred during 2015 through participation observation, semi-structured interviews, and a convergence group. Analysis comprised the phases Apprehension, Synthesis, Theorization, and Transference. four categories emerged. They showed satisfaction and dissatisfaction related to identification with tasks and work content, material and personal gains obtained from solid waste segregation, prejudice, lack of appreciation, and difficulties in interpersonal relationships. This last item, due to its importance, received a nursing action. the study contributed to the advancement of knowledge and the association of possibilities between the research performance and nursing care for workers.
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International Nuclear Information System (INIS)
1982-02-01
The emphasis of the work is on the development and characterization of waste products suitable for final storage, such as actinides and fission products from MAW/LAW, as well as on the development of methods for the treatment and solidification of radioactive wastes, e.g. wet chemical oxidation, vitrification and cementation. Investigations on the HAW-storage in salt are carried out in cooperation with the GSF. (HP) [de
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Working on an assured future: the control in Western-Europe of radioactive waste
International Nuclear Information System (INIS)
Boekschoten, H.
1989-01-01
This report presents background information with regard to the policy concerning the disposal and storage of radioactive waste. Also is outlined how this is being worked on by the various European countries which are joined in the UNIPEDE. (author). 60 figs.; 1 tab
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Energy Technology Data Exchange (ETDEWEB)
Neau, H-J.; Bonnardel-Azzarelli, B. [World Nuclear Transport Inst., London (United Kingdom)
2014-07-01
Various kinds of radioactive waste are generated from nuclear power and fuel cycle facilities. These materials have to be treated, stored and eventually sent to a repository site. Transport of wastes between these various stages is crucial for the sustainable utilization of nuclear energy. The IAEA Regulations for the Safe Transport of Radioactive Material (SSR-6) have, for many decades, provided a safe and efficient framework for radioactive materials transport and continue to do so. However, some shippers have experienced that in the transport of certain specific radioactive wastes, difficulties can be encountered. For example, some materials produced in the decommissioning of nuclear facilities are unique in terms of composition or size and can be difficult to characterize as surface contaminated objects (SCO) or homogeneous. One way WNTI (World Nuclear Transport Institute) helps develop transport methodologies is through the use of Industry Working Groups, bringing together WNTI members with common interests, issues and experiences. The Back-End Transport Industry Working Group focuses on the following issues currently. - Characterization of Waste: techniques and methods to classify wastes - Large Objects: slightly contaminated large objects (ex. spent steam generators) transport - Dual Use Casks: transportable storage casks for spent nuclear fuels, including the very long term storage of spent fuel - Fissile Exceptions: new fissile exceptions provisions of revised TS-R-1 (SSR-6) The paper gives a broad overview of current issues for the packaging and transport of radioactive wastes and the associated work of the WNTI. (author)
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Directory of Open Access Journals (Sweden)
Alexa Pupiara Flores Coelho
Full Text Available ABSTRACT Objectives: describe elements that promote satisfaction and dissatisfaction in the work of recyclable solid waste segregators and conduct a nursing action focused on these elements. Method: qualitative research, convergent-care, conducted with members of the cooperative. Data production occurred during 2015 through participation observation, semi-structured interviews, and a convergence group. Analysis comprised the phases Apprehension, Synthesis, Theorization, and Transference. Results: four categories emerged. They showed satisfaction and dissatisfaction related to identification with tasks and work content, material and personal gains obtained from solid waste segregation, prejudice, lack of appreciation, and difficulties in interpersonal relationships. This last item, due to its importance, received a nursing action. Conclusion: the study contributed to the advancement of knowledge and the association of possibilities between the research performance and nursing care for workers.
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International Nuclear Information System (INIS)
1987-09-01
The Second FY87 Meeting of the National Working Group for Reduction in Transuranic Waste Arisings (NWGRTWA) was held at the Lawrence Livermore National Laboratory, Tuesday and Wednesday, July 28--29, 1987. The purpose of the meeting was to discuss (1) modeling programs for waste reduction, (2) proposed FY88 and out-year tasks including the SRL Pu incineration, immobilization improvement, erbia coating technology, and (3) improvements in up-stream recovery operations to effect waste reduction. In addition, tours were made of the LLNL Waste Operations, the Laser Fusion (NOVA), and the Magnetic Fusion (MFTF)
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International Nuclear Information System (INIS)
1997-10-01
Plans for disposing of radioactive wastes have raised a number of unique and mostly philosophical problems, mainly due to the very long time-scales which have to be considered. While there is general agreement on disposal concepts and on many aspects of a safety philosophy, consensus on a number of issues remains to be achieved. The IAEA established a subgroup under the International Radioactive Waste Management Advisory Committee (INWAC). The subgroup started its work in 1991 as the ''INWAC Subgroup on Principles and Criteria for Radioactive Waste Disposal''. With the reorganization in 1995 of IAEA senior advisory committees in the nuclear safety area, the title of the group was changed to ''Working Group on Principles and Criteria for Radioactive Waste Disposal''. The working group is intended to provide an open forum for: (1) the discussion and resolution of contentious issues, especially those with an international component, in the area of principles and criteria for safe disposal of waste; (2) the review and analysis of new ideas and concepts in the subject area; (3) establishing areas of consensus; (4) the consideration of issues related to safety principles and criteria in the IAEA's Radioactive Waste Safety Standards (RADWASS) programme; (5) the exchange of information on national safety criteria and policies for radioactive waste disposal. This is the third report of the working group and it deals with the subject of regulatory decision making under conditions of uncertainty which is a matter of concern with respect to disposal of radioactive wastes underground. 14 refs
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International Nuclear Information System (INIS)
1977-05-01
A scope of work and a venture guidance appraisal were prepared for a conceptual process and plant facilities for the solidification and long-term storage of radioactive wastes removed from underground storage tanks in the 241 F and H Areas at the Savannah River Plant. Conceptual design was based on incorporating the highly radioactive waste components in a borosilicate type glass. The scope of work describes facilities for: reclaiming liquid and sludge wastes from F and H area tank farms; separating the sludge from the liquid salt solution by physical processes; removing radioactive cesium from the salt solution by ion exchange techniques; incorporating the dried sludge and cesium in a borosilicate glass in stainless steel containers; evaporating the liquid salt solution and encapsulating the resulting salt cake in a stainless steel container; and storing two years' worth of glass and salt containing cyclinders in separate retrievable surface storage facilities. Operations are to be located in a new area, designated the 200-S area. A full complement of power, general, and service facilities are provided. The venture guidance appraisal based on FY 82 authorization and FY 87 turnover is $2,900,000,000. The figure is suitable for planning purposes only. The Glass-form Waste Case is a variation of the concrete-form waste case (or the Reference Plant Case) reported in DPE--3410. The new venture guidance appraisal for the concrete-form case (updated to a consistent time basis with the glass-form case) is $2,900,000,000, indicating no apparent cost advantage between the two waste product forms
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International Nuclear Information System (INIS)
Trofimenko, A.P.; Pisanko, Zh.I.
2000-01-01
INIS information database was used for study the problem of high-level radioactive waste management . The main directions of works were determined by the subject content of the mostly used key-words to particular publications. The problems of site selection for waste storage, ecological and social aspects of waste management role of particular radionuclides in it were studied. Dynamics of work development in time, and contribution of different countries, in particular Russia and Ukraine, in this problem were considered
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Glass-Ceramic Waste Forms for Uranium and Plutonium Residues Wastes - 13164
International Nuclear Information System (INIS)
Stewart, Martin W.A.; Moricca, Sam A.; Zhang, Yingjie; Day, R. Arthur; Begg, Bruce D.; Scales, Charlie R.; Maddrell, Ewan R.; Hobbs, Jeff
2013-01-01
A program of work has been undertaken to treat plutonium-residues wastes at Sellafield. These have arisen from past fuel development work and are highly variable in both physical and chemical composition. The principal radiological elements present are U and Pu, with small amounts of Th. The waste packages contain Pu in amounts that are too low to be economically recycled as fuel and too high to be disposed of as lower level Pu contaminated material. NNL and ANSTO have developed full-ceramic and glass-ceramic waste forms in which hot-isostatic pressing is used as the consolidation step to safely immobilize the waste into a form suitable for long-term disposition. We discuss development work on the glass-ceramic developed for impure waste streams, in particular the effect of variations in the waste feed chemistry glass-ceramic. The waste chemistry was categorized into actinides, impurity cations, glass formers and anions. Variations of the relative amounts of these on the properties and chemistry of the waste form were investigated and the waste form was found to be largely unaffected by these changes. This work mainly discusses the initial trials with Th and U. Later trials with larger variations and work with Pu-doped samples further confirmed the flexibility of the glass-ceramic. (authors)
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International Nuclear Information System (INIS)
Collins, E.; Duguid, J.; Henry, R.; Karell, E.J.; Laidler, J.J.; McDeavitt, S.M.; Thompson, M.; Toth, L.M.; Williamson, M.; Willit, J.L.
1999-01-01
In response to a Congressional mandate to prepare a roadmap for the development of Accelerator Transmutation of Waste (ATW) technology, a Technical Working Group comprised of members from various DOE laboratories was convened in March 1999 for the purpose of preparing that part of the technology development roadmap dealing with the separation of certain radionuclides for transmutation and the disposal of residual radioactive wastes from these partitioning operations. The Technical Working Group for ATW Separations Technologies and Waste Forms completed its work in June 1999, having carefully considered the technology options available. A baseline process flowsheet and backup process were identified for initial emphasis in a future research, development and demonstration program. The baseline process combines aqueous and pyrochemical processes to permit the efficient separation of the uranium, technetium, iodine and transuranic elements from the light water reactor (LWR) fuel in the head-end step. The backup process is an all- pyrochemical system. In conjunction with the aqueous process, the baseline flowsheet includes a pyrochemical process to prepare the transuranic material for fabrication of the ATW fuel assemblies. For the internal ATW fuel cycle the baseline process specifies another pyrochemical process to extract the transuranic elements, Tc and 1 from the ATW fuel. Fission products not separated for transmutation and trace amounts of actinide elements would be directed to two high-level waste forms, one a zirconium-based alloy and the other a glass/sodalite composite. Baseline cost and schedule estimates are provided for a RD and D program that would provide a full-scale demonstration of the complete separations and waste production flowsheet within 20 years
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Energy Technology Data Exchange (ETDEWEB)
Collins, E.; Duguid, J.; Henry, R.; Karell, E.; Laidler, J.; McDeavitt, S.; Thompson, M.; Toth, M.; Williamson, M.; Willit, J.
1999-08-12
In response to a Congressional mandate to prepare a roadmap for the development of Accelerator Transmutation of Waste (ATW) technology, a Technical Working Group comprised of members from various DOE laboratories was convened in March 1999 for the purpose of preparing that part of the technology development roadmap dealing with the separation of certain radionuclides for transmutation and the disposal of residual radioactive wastes from these partitioning operations. The Technical Working Group for ATW Separations Technologies and Waste Forms completed its work in June 1999, having carefully considered the technology options available. A baseline process flowsheet and backup process were identified for initial emphasis in a future research, development and demonstration program. The baseline process combines aqueous and pyrochemical processes to permit the efficient separation of the uranium, technetium, iodine and transuranic elements from the light water reactor (LWR) fuel in the head-end step. The backup process is an all- pyrochemical system. In conjunction with the aqueous process, the baseline flowsheet includes a pyrochemical process to prepare the transuranic material for fabrication of the ATW fuel assemblies. For the internal ATW fuel cycle the baseline process specifies another pyrochemical process to extract the transuranic elements, Tc and 1 from the ATW fuel. Fission products not separated for transmutation and trace amounts of actinide elements would be directed to two high-level waste forms, one a zirconium-based alloy and the other a glass/sodalite composite. Baseline cost and schedule estimates are provided for a RD&D program that would provide a full-scale demonstration of the complete separations and waste production flowsheet within 20 years.
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International Nuclear Information System (INIS)
Xi, Huan; Li, Ming-Jia; He, Ya-Ling; Tao, Wen-Quan
2015-01-01
In the present study, we proposed a graphical criterion called CE diagram by achieving the Pareto optimal solutions of the annual cash flow and exergy efficiency. This new graphical criterion enables both working fluid selection and thermodynamic system comparison for waste heat recovery. It's better than the existing criterion based on single objective optimization because it is graphical and intuitionistic in the form of diagram. The features of CE diagram were illustrated by studying 5 examples with different heat-source temperatures (ranging between 100 °C to 260 °C), 26 chlorine-free working fluids and two typical ORC systems including basic organic Rankine cycle(BORC) and recuperative organic Rankine cycle (RORC). It is found that the proposed graphical criterion is feasible and can be applied to any closed loop waste heat recovery thermodynamic systems and working fluids. - Highlights: • A graphical method for ORC system comparison/working fluid selection was proposed. • Multi-objectives genetic algorithm (MOGA) was applied for optimizing ORC systems. • Application cases were performed to demonstrate the usage of the proposed method.
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Working towards a universal container for category B waste
International Nuclear Information System (INIS)
Tallec, M.
2002-01-01
Long-lived, intermediate-level waste, known as category 8 waste, accounts for most long lived waste (> 90%), although it only accounts for a very small fraction of radiotoxicity (< 10%). It comes in a wide variety of forms. The first step to be taken is to classify it into a few families and define a standard management mode for each one. Research teams are therefore seeking to propose a range of universal containers for existing packages and waste still to be conditioned. (author)
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The health hazards of depleted uranium munitions. Part 1
Energy Technology Data Exchange (ETDEWEB)
NONE
2001-05-01
There has been a substantial amount of public discussion on the health effects of the use of depleted uranium (DU), especially on the battlefield. The RoyaI Society therefore convened an independent expert Working Group to review the present state of scientific knowledge about the health and environmental effects of DU, in order to inform public debate. This is the first of two reports. It deals with the amounts of DU to which soldiers could be exposed on the battlefield, the risks from radiation, and what we know from epidemiological studies. We consider past and potential future exposures, the most likely exposures and the 'worst-case' exposures that cannot be excluded. Our second report, to be published later this year, will address the risks from toxic poisoning and environmental issues including risks to civilian populations. The group has consulted widely. It has focused on what is known scientifically about aspects that are relevant to health and has not considered the merits of using DU in munitions. Nor does this report analyse Gulf War syndrome, which has been the subject of other reports. DU is a toxic and weakly radioactive heavy metal that may have adverse consequences to human health, particularly if it enters the body through inhalation, ingestion or wounding. On the battlefield it is used in kinetic energy weapons designed to penetrate the armour of tanks and other vehicles. On impact substantial amounts of DU may be dispersed as particles that can be inhaled and as shrapnel. Our approach has been to estimate the typical levels of exposure on the battlefield over a wide range of scenarios, and the worst-case exposures that individuals are unlikely to exceed. From these we calculate the potential health risks from radiation. We have also considered epidemiological studies of occupational exposures to uranium in other situations as an independent source of information on the risks of inhaling DU particles, although we recognise that the
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The health hazards of depleted uranium munitions. Part 1
International Nuclear Information System (INIS)
2001-01-01
There has been a substantial amount of public discussion on the health effects of the use of depleted uranium (DU), especially on the battlefield. The RoyaI Society therefore convened an independent expert Working Group to review the present state of scientific knowledge about the health and environmental effects of DU, in order to inform public debate. This is the first of two reports. It deals with the amounts of DU to which soldiers could be exposed on the battlefield, the risks from radiation, and what we know from epidemiological studies. We consider past and potential future exposures, the most likely exposures and the 'worst-case' exposures that cannot be excluded. Our second report, to be published later this year, will address the risks from toxic poisoning and environmental issues including risks to civilian populations. The group has consulted widely. It has focused on what is known scientifically about aspects that are relevant to health and has not considered the merits of using DU in munitions. Nor does this report analyse Gulf War syndrome, which has been the subject of other reports. DU is a toxic and weakly radioactive heavy metal that may have adverse consequences to human health, particularly if it enters the body through inhalation, ingestion or wounding. On the battlefield it is used in kinetic energy weapons designed to penetrate the armour of tanks and other vehicles. On impact substantial amounts of DU may be dispersed as particles that can be inhaled and as shrapnel. Our approach has been to estimate the typical levels of exposure on the battlefield over a wide range of scenarios, and the worst-case exposures that individuals are unlikely to exceed. From these we calculate the potential health risks from radiation. We have also considered epidemiological studies of occupational exposures to uranium in other situations as an independent source of information on the risks of inhaling DU particles, although we recognise that the parallels may
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Statement of work for the immobilized high-level waste transportation system, Project W-464
Energy Technology Data Exchange (ETDEWEB)
Mouette, P.
1998-06-24
The objective of this Statement of Work (SOW) is to present the scope, the deliverables, the organization, the technical and schedule expectations for the development of a Package Design Criteria (PDC), cost and schedule estimate for the acquisition of a transportation system for the Immobilized High-Level Waste (IHLW). This transportation system which includes the truck, the trailer, and a shielded cask will be used for on-site transportation of the IHLW canisters from the private vendor vitrification facility to the Hanford Site interim storage facility, i.e., vaults 2 and 3 of the Canister Storage Building (CSB). This Statement of Work asks Waste Management Federal Services, Inc., Northwest Operations, to provide Project W-464 with a Design Criteria Document, plus a life-cycle schedule and cost estimate for the acquisition of a transportation system (shielded cask, truck, trailer) for IHLW on-site transportation.
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Focal points of future FuE work concerning the final disposal of radioactive wastes (2011-2014)
International Nuclear Information System (INIS)
2012-07-01
The present Federal support concept is the basis for applied fundamental research concerning final disposal of heat generating radioactive wastes. The use-oriented fundamental research is aimed to the development of a scientific-technical basis for the realization of a final repository for heat-generating radioactive wastes and spent nuclear fuel, to the continuous advancement of the state of science and technology with respect to final waste disposal and a substantial contribution to the constitution, development and preservation of scientific-technological competence in the field of nuclear waste management in Germany. The concept includes research and development work concerning final disposal in the host rock salt, clays and crystalline rocks (granite). The research and development main issues are the final disposal system, the system behavior, further topics in relation to final disposal and nuclear materials surveillance.
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Sectored Clean-up Work Plan for Housekeeping Category Waste Sites
International Nuclear Information System (INIS)
Nacht, S. J.
2000-01-01
The Sectored Clean-up Work Plan (SCWP) replaces the Housekeeping Category Corrective Action Unit Work Plan and provides a strategy to be used for conducting housekeeping activities using a sectored clean-up approach. This work plan provides a process by which one or more existing housekeeping category Corrective Action Sites (CASS) from the Federal Facility Agreement and Consent Order and/or non-FFACO designated waste site(s) are grouped into a sector for simultaneous remediation and cleanup. This increases effectiveness and efficiencies in labor, materials, equipment, cost, and time. This plan is an effort by the U.S. Department of Energy to expedite work in a more organized and efficient approach. The objectives of this plan are to: Group housekeeping FFACO CASS and non-FFACO housekeeping sites into sectors and remediate during the same field visit; Provide consistent documentation on FFACO CAS and non-FFACO clean-up activities; Perform similar activities under one approved document; Remediate areas inside the Deactivation and Decommissioning facilities and compounds in a campaign-style remediation; and Increase efficiencies and cost-effectiveness, accelerate cleanups, reduce mobilization, demobilization, and remediation costs
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International Nuclear Information System (INIS)
Conley, T.B.; Morris, M.I.; Holmes-Burns, H.; Petersell, J.; Schwendiman, L.
1997-01-01
In May 1996, the U.S. Department of Energy (DOE) Mixed Waste Focus Area (MWFA) initiated the Mercury Work Group (HgWG), which was established to address and resolve the issues associated with mercury- contaminated mixed wastes. Three of the first four technology deficiencies identified during the MWFA technical baseline development process were related to mercury amalgamation, stabilization, and separation/removal. The HgWG will assist the MWFA in soliciting, identifying, initiating, and managing all the efforts required to address these deficiencies. The focus of the HgWG is to better establish the mercury-related treatment needs at the DOE sites, refine the MWFA technical baseline as it relates to mercury treatment, and make recommendations to the MWFA on how to most effectively address these needs. The team will initially focus on the sites with the most mercury-contaminated mixed wastes, whose representatives comprise the HgWG. However, the group will also work with the sites with less inventory to maximize the effectiveness of these efforts in addressing the mercury- related needs throughout the entire complex
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Garrett, Benjamin
1999-10-01
What do Knute Rockne, Notre Dame's famed football coach, and Lewisite, a chemical warfare agent dubbed "the dew of death", have in common? Both owe their discovery to Father Julius Arthur Nieuwland.1 Rockne's legacy lives on in the Fighting Irish and their tradition of excellence on the gridiron. Lewisite, together with other arsenical- and mustard-type chemical warfare agents, provide a legacy that lives on, too, but with less cheerful consequences. The book Arsenic and Old Mustard: Chemical Problems of Old Arsenical and 'Mustard' Munitions makes clear the challenges faced in dealing with those consequences. This book documents the proceedings of a workshop devoted to arsenical- and mustard-type chemical warfare agents and their associated munitions. The workshop, held in Poland in 1996, included nine lectures, eight posters, and three discussion groups; and the contents of all these are presented. Major support for the workshop came from the Scientific Affairs Division of NATO as part of on ongoing series of meetings, cooperative research projects, and related efforts dealing with problems leftover from the Cold War and, in the case of the arsenicals and mustards, from conflicts dating to World War I. These problems can be seen in contemporary accounts, including a January 1999 news report that the U.S. Department of Defense intends to survey Washington, DC, areas near both American University and the Catholic University of America (CUA), site of the original synthesis of Lewisite, for chemical warfare agents and other materials disposed at the end of World War I.2 The first nine chapters of the book present the workshop's lectures. Of these, readers interested in chemical weapon destruction might find especially useful the first chapter, in which Ron Mansley of the Organisation for the Prohibition of Chemical Weapons presents a scholarly overview covering historical aspects of the arsenicals and mustards; their production and use; prospective destruction
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Management of waste from packaging of construction materials in building construction works
González Pericot, Natalia; Río Merino, Mercedes del
2011-01-01
Every material arriving at the construction site comes protected in some type of packaging, fundamentally cardboard, plastic or wood, and presently the great majority of these packagings finish in a container mixed with the rest of waste of the construction work. The increasing tendency to use prefabricated materials increases the volume of packaging necessary in product transport; in addition, the traditional materials also arrive more protected with packaging. A specific management for ...
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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
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International Nuclear Information System (INIS)
Hodgson, K.M.
1996-01-01
This work plan addresses the Standard Inventory task scope, deliverables, budget, and schedule for fiscal year 1997. The goal of the Standard Inventory task is to resolve differences among the many reported Hanford Site tank waste inventory values and to provide inventory estimates that will serve as Standard Inventory values for all waste management and disposal activities. These best-basis estimates of chemicals and radionuclides will be reported on both a global and tank-specific basis and will be published in the Tank Characterization Database
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International Nuclear Information System (INIS)
Li, You-Rong; Du, Mei-Tang; Wu, Chun-Mei; Wu, Shuang-Ying; Liu, Chao
2014-01-01
The performance of the ORC (organic Rankine cycle) systems using zeotropic mixtures as working fluids for recovering waste heat of flue gas from industrial boiler is examined on the basis of thermodynamics and thermo-economics under different operating conditions. In order to explore the potential of the mixtures as the working fluids in the ORC, the effects of various mixtures with different components and composition proportions on the system performance have been analyzed. The results show that the compositions of the mixtures have an important effect on the ORC system performance, which is associated with the temperature glide during the phase change of mixtures. From the point of thermodynamics, the performance of the ORC system is not always improved by employing the mixtures as the working fluids. The merit of the mixtures is related to the restrictive conditions of the ORC, different operating conditions results in different conclusions. At a fixed pinch point temperature difference, the small mean heat transfer temperature difference in heat exchangers will lead to a larger heat transfer area and the larger total cost of the ORC system. Compared with the ORC with pure working fluids, the ORC with the mixtures presents a poor economical performance. - Highlights: • Organic Rankine cycle system with the mixture working fluids for recovering waste heat is analyzed. • The performance of the mixture-fluid ORC is related to temperature glide in phase change of mixture working fluids. • The relative merit of the mixture working fluids depends on the restrictive operation conditions of the ORC. • The ORC with mixture working fluid presents a poor economical performance compared with the pure working fluid case
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Directory of Open Access Journals (Sweden)
Smitka Martin
2014-03-01
Full Text Available One of the options on how to remove waste heat from electronic components is using loop heat pipe. The loop heat pipe (LHP is a two-phase device with high effective thermal conductivity that utilizes change phase to transport heat. It was invented in Russia in the early 1980’s. The main parts of LHP are an evaporator, a condenser, a compensation chamber and a vapor and liquid lines. Only the evaporator and part of the compensation chamber are equipped with a wick structure. Inside loop heat pipe is working fluid. As a working fluid can be used distilled water, acetone, ammonia, methanol etc. Amount of filling is important for the operation and performance of LHP. This work deals with the design of loop heat pipe and impact of filling ratio of working fluid to remove waste heat from insulated gate bipolar transistor (IGBT.
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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.
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Methodology for quantification of waste generated in Spanish railway construction works.
de Guzmán Báez, Ana; Villoria Sáez, Paola; del Río Merino, Mercedes; García Navarro, Justo
2012-05-01
In the last years, the European Union (EU) has been focused on the reduction of construction and demolition (C&D) waste. Specifically, in 2006, Spain generated roughly 47million tons of C&D waste, of which only 13.6% was recycled. This situation has lead to the drawing up of many regulations on C&D waste during the past years forcing EU countries to include new measures for waste prevention and recycling. Among these measures, the mandatory obligation to quantify the C&D waste expected to be originated during a construction project is mandated. However, limited data is available on civil engineering projects. Therefore, the aim of this research study is to improve C&D waste management in railway projects, by developing a model for C&D waste quantification. For this purpose, we develop two equations which estimate in advance the amount, both in weight and volume, of the C&D waste likely to be generated in railway construction projects, including the category of C&D waste generated for the entire project. Copyright © 2012 Elsevier Ltd. All rights reserved.
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Korean working towards low and intermediate level waste volume reduction
International Nuclear Information System (INIS)
Myung-Jae Song; Jong-Kil Park
2001-01-01
The safe management of radioactive waste is a national task required for sustainable generation of nuclear power and for energy self-reliance. This paper describes the results, efforts, and prospects for the safe management of radioactive wastes having been performed by the Nuclear Environment Technology Institute (NETEC) of the Korean Electric Power Corporation (KEPCO). Firstly, KEPCO's efforts and results for waste volume reduction are summarized to show how the number of waste drums generated per reactor-year could be reduced by about 60% during the last 10 years. Secondly, a new treatment technology, a technology for low and intermediate level waste (LILW) vitrification, was introduced to prospect how the technology reduces the waste volume and increases the inherent safety for LILW disposal. It is expected that the vitrification technology will contribute not only to reduce LILW volume to around 1/14 ∼ 1/32 but also to change the 'Not In My Back Yard' (NIMBY) syndrome to the 'Please In My Front Yard' (PIMFY) attitude of local communities/residents for LILW disposal. (author)
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Energy Technology Data Exchange (ETDEWEB)
Leung, F.; Cataldo, D.A.; Fellows, R.J.; Jarrell, A.E.; Harvey, S.D.
1995-09-01
Munitions material can enter the environment as a result of manufacturing activities and field usage. Predictor methodologies, or biomarkers would enhance evaluation of environmental impacts. The goal of this exploratory study deoxyribonucleic acid (DNA) mutation frequency as a biomarker for munitions exposure. The approach e resolution of an effective repetitive sequence probe for the identification of characteristic mutations, and (2) the development of a testing media [a clonal cell line of carrot (Daucus carota) spension cells]. Commercially available probes demonstrated marginal resolution therefore a low-C{sub o}t library was then constructed. Three colonies from the low-C{sub o}t DNA library were screened and the DNA isolates sequenced. A suspension culture of carrot (Daucus carota) was developed. A mutation spectra experiment was initiated at a 10-mg TNT/L exposure concentration with the attempt to clone over 1500 single TNT-exposed cells. Over the following six months greater than 98% of the initially isolated cells were unable to survive and produce micro calluses. The remaining calli were too few to be statistically significant and the experiment was terminated. The biomarker concept itself remains to be disproved, but the need for large numbers of uniform clones to differentiate true mutations suggest that more direct techniques using whole tissues need to be developed.
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International Nuclear Information System (INIS)
LaFemina, J.P.; Blanchard, D.L.; Bunker, B.C.; Colton, N.G.; Felmy, A.R.; Franz, J.A.; Liu, J.; Virden, J.W.
1994-01-01
Remediation efforts at the U.S. Department of Energy's Hanford Site require that many technical and scientific principles be combined for effectively managing and disposing the variety of wastes currently stored in underground tanks. Based on these principles, pretreatment technologies are being studied and developed to separate waste components and enable the most suitable treatment methods to be selected for final disposal of these wastes. The Tank Waste Treatment Science Task at Pacific Northwest Laboratory is addressing pretreatment technology development by investigating several aspects related to understanding and processing the tank contents. The experimental work includes evaluating the chemical and physical properties of the alkaline wastes, modeling sludge dissolution, and evaluating and designing ion exchange materials. This paper gives some examples of results of this work and shows how these results fit into the overall Hanford waste remediation activities. This work is part of series of projects being conducted for the Tank Waste Remediation System
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Updated Liquid Secondary Waste Grout Formulation and Preliminary Waste Form Qualification
Energy Technology Data Exchange (ETDEWEB)
Saslow, Sarah A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Um, Wooyong [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Russell, Renee L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wang, Guohui [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Asmussen, Robert M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sahajpal, Rahul [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
2017-07-01
This report describes the results from liquid secondary waste grout (LSWG) formulation and cementitious waste form qualification tests performed by Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions, LLC (WRPS). New formulations for preparing a cementitious waste form from a high-sulfate liquid secondary waste stream simulant, developed for Effluent Management Facility (EMF) process condensates merged with low activity waste (LAW) caustic scrubber, and the release of key constituents (e.g. 99Tc and 129I) from these monoliths were evaluated. This work supports a technology development program to address the technology needs for Hanford Site Effluent Treatment Facility (ETF) liquid secondary waste (LSW) solidification and supports future Direct Feed Low-Activity Waste (DFLAW) operations. High-priority activities included simulant development, LSWG formulation, and waste form qualification. The work contained within this report relates to waste form development and testing and does not directly support the 2017 integrated disposal facility (IDF) performance assessment (PA). However, this work contains valuable information for use in PA maintenance past FY17, and for future waste form development efforts. The provided data should be used by (i) cementitious waste form scientists to further understanding of cementitious dissolution behavior, (ii) IDF PA modelers who use quantified constituent leachability, effective diffusivity, and partitioning coefficients to advance PA modeling efforts, and (iii) the U.S. Department of Energy (DOE) contractors and decision makers as they assess the IDF PA program. The results obtained help fill existing data gaps, support final selection of a LSWG waste form, and improve the technical defensibility of long-term waste form performance estimates.
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African Journals Online (AJOL)
Administrator
Government Areas in Delta State of Nigeria were bioremediated using mycofiltration technique. Statistical ... mainly microorganisms (yeast, fungi or bacteria) ... pollutants, including pesticides, munitions waste, ... Akpaja and Olorunfemi: Mycofiltration Effectiveness in Bioremediation of Contaminated Drinking Water Sources ...
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International Nuclear Information System (INIS)
Kobayashi, Kentarou; Isozaki, Kouei; Akutu, Shigeru; Nakanishi, Masahiro; Ozone, Takashi; Terunuma, Tomomi
2003-04-01
This document is announced about task of Waste Management Division Waste Management Section in the 2002 fiscal year. Mainly, our task is that treated Low level solid waste, stored Low level solid waste and stored High level solid waste. Those wastes are generated from Tokai reprocessing plant in Tokai Works. We carried out task safely as planned. The results are as follows. (1) We incinerated that combustible Low level solid waste of 70.5 ton in Incinerate facility. Such wastes were generated from operation of Tokai reprocessing plant and cleaned up operation of Tokai bituminization facility (The fire and explosion incident of Tokai bituminization facility). (2) We stored Low level solid waste that generated the waste of 1,071 drums. It is found that Storage facilities will not fill on this condition Low level radioactive waste treatment facility is started operation. (3) We stored High level solid waste that generated the waste of 117 drums from Tokai reprocessing plant. And, it is found that there facilities will not fill on this condition generated wastes of about 100 drams by a year. (4) We started printing of the data from the 2002 fiscal year to intranet which amount of stored Low level solid waste and High level solid waste in order to educate-the amount reduction of waste generating (at those facilities). (author)
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International Nuclear Information System (INIS)
1993-01-01
The Tennessee Department of Environment and Conservation (TDEC) and the Department of Energy (DOE) have made the determination that approximately 258 drums of waste and 10 open-top boxes of waste now located at the site known as David Witherspoon, Inc., (DWI) in south Knoxville, Tennessee, should be repackaged as necessary and transferred to the K-25 Site in Oak Ridge, Tennessee, for management. This work plan addresses the four phases of activity planned and the methods of accomplishment The lint phase will consist of an assessment to determine requirements for managing the waste. Items to be investigated include site access, site conditions, personal protective equipment, waste characterization needs, packaging and labeling, transportation, receipt and storage of the waste at the K-25 Site, and site controls and monitoring required during the packaging operations to be conducted at DWI. The second phase will include mobilization of on-site support and operating facilities, sampling and transferral of a randomly selected representative fraction of the 232 drums now stored on-site in sea/land containers to storage facilities at the K-25 Site, and sampling of the waste now stored in the 26 drums inside the main process building and the 10 open-top boxes of waste stored outside and adjacent to the building. The third phase will include repackaging and transferral of the 26 drums and 10 boxes of waste to the K-25 Site and placement of the containerized waste into appropriate storage at the K-25 Site. Participants in the fourth phase of activity will demobilize the support and operating facilities from DWI, conduct an on-site evaluation at the K-25 site to verify compliance with storage and other management requirements, prepare a closeout report for the activity assessing the actions, and develop a plan for the final management method for the waste
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International Nuclear Information System (INIS)
1999-01-01
The NEA Radioactive Waste Management Committee (RWMC) is a forum of senior operators, regulators, policy makers, and senior representatives of R and D institutions in the field of radioactive waste management. The Committee assists Member countries by providing objective guidance on the solution of radioactive waste problems, and promotes Safety in the short- and long-term management of radioactive waste. This report identifies some of the major challenges currently faced by national waste management programmes, and describes the strategic areas in which the RWMC should focus its efforts in future years. (author)
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International Nuclear Information System (INIS)
Vargo, G.F. Jr.
1995-01-01
The purpose of this work scope is to identify a specific potential technology/device/instrument/ideas that would provide the tank waste data. A method is needed for identifying layering and physical state within the large waste tanks at the Hanford site in Washington State. These interfaces and state changes can adversely impact sampling and characterization activities
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Liquid secondary waste. Waste form formulation and qualification
Energy Technology Data Exchange (ETDEWEB)
Cozzi, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, K. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hill, K. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); King, W. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nichols, R. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
2016-03-01
The Hanford Site Effluent Treatment Facility (ETF) currently treats aqueous waste streams generated during Site cleanup activities. When the Hanford Tank Waste Treatment and Immobilization Plant (WTP) begins operations, a liquid secondary waste (LSW) stream from the WTP will need to be treated. The volume of effluent for treatment at the ETF will increase significantly. Washington River Protection Solutions is implementing a Secondary Liquid Waste Immobilization Technology Development Plan to address the technology needs for a waste form and solidification process to treat the increased volume of waste planned for disposal at the Integrated Disposal Facility IDF). Waste form testing to support this plan is composed of work in the near term to demonstrate the waste form will provide data as input to a performance assessment (PA) for Hanford’s IDF.
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International Nuclear Information System (INIS)
Neilson, R.M. Jr.; Colombo, P.
1982-01-01
Contemporary solidification agents are being investigated relative to their applications to major fuel cycle and non-fuel cycle low-level waste (LLW) streams. Work is being conducted to determine the range of conditions under which these solidification agents can be applied to specific LLW streams. These studies are directed primarily towards defining operating parameters for both improved solidification of problem wastes and solidification of new LLW streams generated from advanced volume reduction technologies. Work is being conducted to measure relevant waste form properties. These data will be compiled and evaluated to demonstrate compliance with waste form performance and shallow land burial acceptance criteria and transportation requirements
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Energy Technology Data Exchange (ETDEWEB)
Saslow, Sarah A.; Um, Wooyong; Russell, Renee L.
2017-08-02
This report describes the results from grout formulation and cementitious waste form qualification testing performed by Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions, LLC (WRPS). These results are part of a screening test that investigates three grout formulations proposed for wide-range treatment of different waste stream compositions expected for the Hanford Effluent Management Facility (EMF) evaporator bottom waste. This work supports the technical development need for alternative disposition paths for the EMF evaporator bottom wastes and future direct feed low-activity waste (DFLAW) operations at the Hanford Site. High-priority activities included simulant production, grout formulation, and cementitious waste form qualification testing. The work contained within this report relates to waste form development and testing, and does not directly support the 2017 Integrated Disposal Facility (IDF) performance assessment (PA). However, this work contains valuable information for use in PA maintenance past FY 2017 and future waste form development efforts. The provided results and data should be used by (1) cementitious waste form scientists to further the understanding of cementitious leach behavior of contaminants of concern (COCs), (2) decision makers interested in off-site waste form disposal, and (3) the U.S. Department of Energy, their Hanford Site contractors and stakeholders as they assess the IDF PA program at the Hanford Site. The results reported help fill existing data gaps, support final selection of a cementitious waste form for the EMF evaporator bottom waste, and improve the technical defensibility of long-term waste form risk estimates.
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Igneous Intrusion Impacts on Waste Packages and Waste Forms
International Nuclear Information System (INIS)
P. Bernot
2004-01-01
The purpose of this model report is to assess the potential impacts of igneous intrusion on waste packages and waste forms in the emplacement drifts at the Yucca Mountain Repository. The model is based on conceptual models and includes an assessment of deleterious dynamic, thermal, hydrologic, and chemical impacts. This constitutes the waste package and waste form impacts submodel of the Total System Performance Assessment for the License Application (TSPA-LA) model assessing the impacts of a hypothetical igneous intrusion event on the repository total system performance. This submodel is carried out in accordance with Technical Work Plan for Waste Form Degradation Modeling, Testing, and Analyses in Support of SR and LA (BSC 2003a) and Total System Performance Assessment-License Application Methods and Approaches (BSC 2002a). The technical work plan is governed by the procedures of AP-SIII.10Q, Models. Any deviations from the technical work plan are documented in the TSPA-LA approach to implementing the models for waste package and waste form response during igneous intrusion is based on identification of damage zones. Zone 1 includes all emplacement drifts intruded by the basalt dike, and Zone 2 includes all other emplacement drifts in the repository that are not in Zone 1. This model report will document the following model: (1) Impacts of magma intrusion on the components of engineered barrier system (e.g., drip shields and cladding) of emplacement drifts in Zone 1, and the fate of waste forms. (2) Impacts of conducting magma heat and diffusing magma gases on the drip shields, waste packages, and cladding in the Zone 2 emplacement drifts adjacent to the intruded drifts. (3) Impacts of intrusion on Zone 1 in-drift thermal and geochemical environments, including seepage hydrochemistry. The scope of this model only includes impacts to the components stated above, and does not include impacts to other engineered barrier system (EBS) components such as the invert and
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Igneous Intrusion Impacts on Waste Packages and Waste Forms
Energy Technology Data Exchange (ETDEWEB)
P. Bernot
2004-08-16
The purpose of this model report is to assess the potential impacts of igneous intrusion on waste packages and waste forms in the emplacement drifts at the Yucca Mountain Repository. The model is based on conceptual models and includes an assessment of deleterious dynamic, thermal, hydrologic, and chemical impacts. This constitutes the waste package and waste form impacts submodel of the Total System Performance Assessment for the License Application (TSPA-LA) model assessing the impacts of a hypothetical igneous intrusion event on the repository total system performance. This submodel is carried out in accordance with Technical Work Plan for Waste Form Degradation Modeling, Testing, and Analyses in Support of SR and LA (BSC 2003a) and Total System Performance Assessment-License Application Methods and Approaches (BSC 2002a). The technical work plan is governed by the procedures of AP-SIII.10Q, Models. Any deviations from the technical work plan are documented in the TSPA-LA approach to implementing the models for waste package and waste form response during igneous intrusion is based on identification of damage zones. Zone 1 includes all emplacement drifts intruded by the basalt dike, and Zone 2 includes all other emplacement drifts in the repository that are not in Zone 1. This model report will document the following model: (1) Impacts of magma intrusion on the components of engineered barrier system (e.g., drip shields and cladding) of emplacement drifts in Zone 1, and the fate of waste forms. (2) Impacts of conducting magma heat and diffusing magma gases on the drip shields, waste packages, and cladding in the Zone 2 emplacement drifts adjacent to the intruded drifts. (3) Impacts of intrusion on Zone 1 in-drift thermal and geochemical environments, including seepage hydrochemistry. The scope of this model only includes impacts to the components stated above, and does not include impacts to other engineered barrier system (EBS) components such as the invert and
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International Nuclear Information System (INIS)
Deju, R.A.; Babad, H.; Bensky, M.S.; Jacobs, G.K.
1983-01-01
The Basalt Waste Isolation Project has developed a method for defining in detail the work required to demonstrate the feasibility of emplacing and providing for the safe isolation of nuclear wastes in a repository in the deep basalts at the Hanford Site near Richland, Washington. Criteria analysis allows the identification of areas of significant technical uncertainty or controversy that can be highlighted as issues. A preliminary analysis has been conducted, which, by identifying key radionuclides and allocating performance among the multiple barriers in a repository constructed in a basalt, allows the design and development testing activities at the Basalt Waste Isolation Project to be put into perspective. Application of sophisticated uncertainty analysis techniques will allow refinements in the analysis to be made and to further guide characterization and testing activities. Preliminary results suggest that a repository constructed in basalt will provide for the safe isolation of nuclear wastes in a cost-effective and reliable manner with a high degree of confidence
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International Nuclear Information System (INIS)
Driver, S.; Griffiths, M.; Leonard, C.D.; Smith, D.L.G.
1992-01-01
This report summarises work carried out on the design of facilities for the quality checking of Intermediate and Low Level Radioactive Waste and Hazardous Waste. The procedures used for the quality checking of these categories of waste are summarised. Three building options are considered: a separate LLW facility, a combined facility for LLW and HW and a Waste Quality Checking Facility for the three categories of waste. Budget Cost Estimates for the three facilities are given based on 1991 prices. (author)
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International Nuclear Information System (INIS)
Guzella, M.F.R.; Miaw, S.T.W.; Reis, L.C.S.; Santos, P.O.; Silva, E.M.P.; Tello, C.C.O.
1988-01-01
Radioactive waste were generated in Goiania by an accidental breakage of Cesium 137 radiotherapie source (A=5,0 x 10 13 Bq) in September 1987. The Waste Treatment Division (DITRR.CN) CDTN/NUCLEBRAS has worked in all critical areas to remove the contamination and carried out the tasks at the interim storage. Experience on the waste management and the results from the R and D works conducted by the Division were applied. The R and D works conducted by the Division were applied. The R and D works conducted by the Division were applied. The R and D works comprise package for storage and transport of radioactive material, the use of selected bentonite for Cesium 137 retention, installation of waste treatment facilities and elaboration of several specific procedures. (author) [pt
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TSA waste stream and final waste form composition
International Nuclear Information System (INIS)
Grandy, J.D.; Eddy, T.L.; Anderson, G.L.
1993-01-01
A final vitrified waste form composition, based upon the chemical compositions of the input waste streams, is recommended for the transuranic-contaminated waste stored at the Transuranic Storage Area of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The quantities of waste are large with a considerable uncertainty in the distribution of various waste materials. It is therefore impractical to mix the input waste streams into an ''average'' transuranic-contaminated waste. As a result, waste stream input to a melter could vary widely in composition, with the potential of affecting the composition and properties of the final waste form. This work examines the extent of the variation in the input waste streams, as well as the final waste form under conditions of adding different amounts of soil. Five prominent Rocky Flats Plant 740 waste streams are considered, as well as nonspecial metals and the ''average'' transuranic-contaminated waste streams. The metals waste stream is the most extreme variation and results indicate that if an average of approximately 60 wt% of the mixture is soil, the final waste form will be predominantly silica, alumina, alkaline earth oxides, and iron oxide. This composition will have consistent properties in the final waste form, including high leach resistance, irrespective of the variation in waste stream. For other waste streams, much less or no soil could be required to yield a leach resistant waste form but with varying properties
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Energy Technology Data Exchange (ETDEWEB)
Harvey, S.D.; Clauss, T.W.; Fellows, R.J.; Cataldo, D.A.
1995-08-01
Genetic damage to deoxyribonucleic acid (DNA) has long been suspected of being a fundamental event leading to cancer. A variety of causal factors can result in DNA damage including photodimerization of base pairs, ionizing radiation, specific reaction of DNA with environmental pollutants, and nonspecific oxidative damage caused by the action of highly reactive oxidizing agents produced by metabolism. Because organisms depend on an unadulterated DNA template for reproduction, DNA repair mechanisms are an important defense for maintaining genomic integrity. The objective of this exploratory project was to evaluate the potential for TNT to form DNA adducts in plants. These adducts, if they exist in sufficient quantities, could be potential biomarkers of munitions exposure. The ultimate goal is to develop a simple analytical assay for the determination of blomarkers that is indicative of munitions contamination. DNA repair exists in dynamic equilibrium with DNA damage. Repair mechanisms are capable of keeping DNA damage at remarkably low concentrations provided that the repair capacity is not overwhelmed.
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DEFF Research Database (Denmark)
Heiselberg, Per; Svidt, Kjeld; Kragh, Hans
In this study CFD was applied to investigate the ability of different ventilation systems and strategies to improve working conditions in a waste incineration plant. The plant, VS Amagerforbn:ending, had expanded to supply both district heating and power. Because of that too high temperatures were...... generated in the working zones and measures to reduce these levels had to be taken ....
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Waste minimization promotes biophysical treatment of complex petrochemical wastes in Israel
Energy Technology Data Exchange (ETDEWEB)
Lebel, A [Invirotreat International Ltd., Fulleron, CA (United States); Raveh, A [Raveh Ecology Ltd., Haifa (Israel)
1994-12-31
This work describes a full-scale waste treatment system which was put into operation in a petrochemical manufacturing plant in Israel for the purpose of detoxifying its complex organic waste stream. The treatment plant design incorporates an innovative waste management approach to accommodate the limited space allocated for the facility. Initial performance data indicate a high efficient inorganic waste reduction. 4 refs., 6 figs., 2 tabs.
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Waste minimization promotes biophysical treatment of complex petrochemical wastes in Israel
Energy Technology Data Exchange (ETDEWEB)
Lebel, A. [Invirotreat International Ltd., Fulleron, CA (United States); Raveh, A. [Raveh Ecology Ltd., Haifa (Israel)
1993-12-31
This work describes a full-scale waste treatment system which was put into operation in a petrochemical manufacturing plant in Israel for the purpose of detoxifying its complex organic waste stream. The treatment plant design incorporates an innovative waste management approach to accommodate the limited space allocated for the facility. Initial performance data indicate a high efficient inorganic waste reduction. 4 refs., 6 figs., 2 tabs.
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Energy Technology Data Exchange (ETDEWEB)
Peek, Dennis W.
2016-02-01
The approach was to perform a document search, supplemented by a visual site inspection, to identify potential environmental contamination associated with the property. Factors evaluated included hazardous substances; petroleum products and derivatives; environmental restoration sites; areas of concern; storage tanks; oil/water separators; grease traps; wash racks; waste tanks; pesticides; military munitions/ordnance; medical or bio-hazardous waste; radioactive waste; solid/municipal waste; indoor air quality; groundwater; wastewater treatment, collection, and disposal/discharge; drinking water quality; utilities; asbestos; polychlorinated biphenyls (PCBs); radon; lead-based paint; cultural resources; floodplains; and natural/biological resources.
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International Nuclear Information System (INIS)
Phuong, H.V.
1976-01-01
One of the several techniques for the disposal of radioactive waste which has been used by some countries, often as a combined international operation, is sea-disposal under carefully controlled conditions. The waste is placed in drums encased in concrete and dumped in selected known ocean areas, currently at least 4000 metres in depth and well away from fishing grounds. The International Atomic Energy Agency is, therefore, directly addressed to by the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter as the competent international body to work out safety criteria, conditions and procedures and to draw up recommendations for the implementation of the Convention with regard to radioactive materials. (author)
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Seminar on R + D work and studies on the disposal and final storage of radioactive waste
International Nuclear Information System (INIS)
1979-10-01
The Seminar had following goals: The research- and development works for safeguarding and final storage of waste are discussed and gone through with regard to their complete processing in due time. A survey on possible co-operation in R+D work is to be set up. The PTB (Physical-technical federal organisation) can normally not order any R+D work nor can it financially support them; it will, however support necessary R+D works with all possibilities it has, for example by sending letters of recommendation and agreement to ministries and other competent institutions. For special investigations relevant for the permission, there are also own means in restricted volume available. (orig./HP) 891 HP/orig.- 892 HIS [de
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Digital Device Architecture and the Safe Use of Flash Devices in Munitions
Katz, Richard B.; Flowers, David; Bergevin, Keith
2017-01-01
Flash technology is being utilized in fuzed munition applications and, based on the development of digital logic devices in the commercial world, usage of flash technology will increase. Digital devices of interest to designers include flash-based microcontrollers and field programmable gate arrays (FPGAs). Almost a decade ago, a study was undertaken to determine if flash-based microcontrollers could be safely used in fuzes and, if so, how should such devices be applied. The results were documented in the Technical Manual for the Use of Logic Devices in Safety Features. This paper will first review the Technical Manual and discuss the rationale behind the suggested architectures for microcontrollers and a brief review of the concern about data retention in flash cells. An architectural feature in the microcontroller under study will be discussed and its use will show how to screen for weak or failed cells during manufacture, storage, or immediately prior to use. As was done for microcontrollers a decade ago, architectures for a flash-based FPGA will be discussed, showing how it can be safely used in fuzes. Additionally, architectures for using non-volatile (including flash-based) storage will be discussed for SRAM-based FPGAs.
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International Nuclear Information System (INIS)
Neilson, R.M. Jr.; Colombo, P.
1982-01-01
In this program, contemporary solidification agents are being investigated relative to their applications to major fuel cycle and non-fuel cycle low-level waste (LLW) streams. Work is being conducted to determine the range of conditions under which these solidification agents can be applied to specific LLW streams. These studies are directed primarily towards defining operating parameters for both improved solidification of problem wastes and solidification of new LLW streams generated from advanced volume reduction technologies. Work is being conducted to measure relevant waste form properties. These data will be compiled and evaluated to demonstrate compliance with waste form performance and shallow land burial acceptance criteria and transportation requirements (both as they exist and as they are modified with time). 6 tables
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DEFF Research Database (Denmark)
Cignitti, Stefano; Andreasen, Jesper Graa; Haglind, Fredrik
2017-01-01
recovery. Inthis paper, an organic Rankine cycle process and its pure working fluid are designed simultaneously forwaste heat recovery of the exhaust gas from a marine diesel engine. This approach can overcome designissues caused by the high sensitivity between the fluid and cycle design variables......Today, some established working fluids are being phased out due to new international regulations on theuse of environmentally harmful substances. With an ever-increasing cost to resources, industry wants toconverge on improved sustainability through resource recovery, and in particular waste heat...
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Yasui, Shojiro
2014-01-01
The accident at the Fukushima Daiichi Atomic Power Plant that accompanied the Great East Japan Earthquake on March 11, 2011, released a large amount of radioactive material. To rehabilitate the contaminated areas, the government of Japan decided to carry out decontamination work and manage the waste resulting from decontamination. In the summer of 2013, the Ministry of the Environment planned to begin a full-scale process for waste disposal of contaminated soil and wastes removed as part of the decontamination work. The existing regulations were not developed to address such a large amount of contaminated wastes. The Ministry of Health, Labour and Welfare (MHLW), therefore, had to amend the existing regulations for waste disposal workers. The amendment of the general regulation targeted the areas where the existing exposure situation overlaps the planned exposure situation. The MHLW established the demarcation lines between the two regulations to be applied in each situation. The amendment was also intended to establish provisions for the operation of waste disposal facilities that handle large amounts of contaminated materials. Deliberation concerning the regulation was conducted when the facilities were under design; hence, necessary adjustments should be made as needed during the operation of the facilities.
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Energy from wastes and the private waste contracting industry
International Nuclear Information System (INIS)
Burnett, J.S.
1993-01-01
The focus of this ongoing work is the utilisation of general non hazardous industrial and commercial waste as an energy or fuel source. Whereas much of the existing experience in energy from waste (EFW) is related to municipal solid wastes (MSW), there is very little direct experience with these other waste streams and the shortage of reliable information in this field is notoriously lacking. It is important to have a good understanding of the private waste contracting industry (pwci) in order to establish the conditions under which energy from waste technologies may play an economically and technically feasible role within that industry's development. The Non Fossil Fuel Obligation (NFFO) has encouraged entrepreneurial interest through premium payments for electricity generated from renewable sources. (author)
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Co-disposal of sewage sludge and solid wastes-it works
Energy Technology Data Exchange (ETDEWEB)
Sussman, D B
1977-10-01
The problem of sludge disposal is one of more sludge than ever before, few suitable land disposal or land application sites, the ocean dumping option being phased out, and energy cost so high or supplies so few as to make incineration a questionable endeavor. The energy required to run a wastewater treatment plant and the heat needed to incinerate the sludge may be available in the same community in the form of municipal solid waste. Municipal sludge has a heat value of about 10,000 Btu/lb of dry solids; it is autogenous at>30% solids. Codisposal techniques are discussed which use the energy produced by the combustion of solid waste to dewater the sludge to its autogenous point. One approach is to use sewage sludge incinerators, in many cases already installed at the wastewater treatment plant, and to use the organic portion of solid waste as a fuel to dry, burn, and reduce the volume of the sludge that must ultimately be disposed. A second approach would use a solid waste incinerator, solid waste-fired steam generator, or waterwall combustion unit to burn dewatered sludge. Both approaches are being demonstrated or used. Thermal sludge disposal at wastewater treatment plants normally is carried out in multiple-hearth or fluidized-bed incinerators. The experiences of such plants in the US and Europe are summarized.
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Technical area status report for low-level mixed waste final waste forms
International Nuclear Information System (INIS)
Mayberry, J.L.; DeWitt, L.M.; Darnell, R.
1993-08-01
The Final Waste Forms (FWF) Technical Area Status Report (TASR) Working Group, the Vitrification Working Group (WG), and the Performance Standards Working Group were established as subgroups to the FWF Technical Support Group (TSG). The FWF TASR WG is comprised of technical representatives from most of the major DOE sites, the Nuclear Regulatory Commission (NRC), the EPA Office of Solid Waste, and the EPA's Risk Reduction Engineering Laboratory (RREL). The primary activity of the FWF TASR Working Group was to investigate and report on the current status of FWFs for LLNM in this TASR. The FWF TASR Working Group determined the current status of the development of various waste forms described above by reviewing selected articles and technical reports, summarizing data, and establishing an initial set of FWF characteristics to be used in evaluating candidate FWFS; these characteristics are summarized in Section 2. After an initial review of available information, the FWF TASR Working Group chose to study the following groups of final waste forms: hydraulic cement, sulfur polymer cement, glass, ceramic, and organic binders. The organic binders included polyethylene, bitumen, vinyl ester styrene, epoxy, and urea formaldehyde. Section 3 provides a description of each final waste form. Based on the literature review, the gaps and deficiencies in information were summarized, and conclusions and recommendations were established. The information and data presented in this TASR are intended to assist the FWF Production and Assessment TSG in evaluating the Technical Task Plans (TTPs) submitted to DOE EM-50, and thus provide DOE with the necessary information for their FWF decision-making process. This FWF TASR will also assist the DOE and the MWIP in establishing the most acceptable final waste forms for the various LLMW streams stored at DOE facilities
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International Nuclear Information System (INIS)
Claxton, D.G.S.A.
1989-03-01
The objectives of the programme where to evaluate potential waste products arising from the conditioning of intermediate-level radioactive wastes/high-level radioactive wastes, and to develop appropriate techniques which could be used to check the quality of the finished waste product. (author)
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IGNEOUS INTRUSION IMPACTS ON WASTE PACKAGES AND WASTE FORMS
International Nuclear Information System (INIS)
Bernot, P.
2004-01-01
The purpose of this model report is to assess the potential impacts of igneous intrusion on waste packages and waste forms in the emplacement drifts at the Yucca Mountain Repository. The models are based on conceptual models and includes an assessment of deleterious dynamic, thermal, hydrologic, and chemical impacts. The models described in this report constitute the waste package and waste form impacts submodel of the Total System Performance Assessment for the License Application (TSPA-LA) model assessing the impacts of a hypothetical igneous intrusion event on the repository total system performance. This submodel is carried out in accordance with Technical Work Plan for Waste Form Degradation Modeling, Testing, and Analyses in Support of LA (BSC 2004 [DIRS:167796]) and Total System Performance Assessment-License Application Methods and Approaches (BSC 2003 [DIRS: 166296]). The technical work plan was prepared in accordance with AP-2.27Q, Planning for Science Activities. Any deviations from the technical work plan are documented in the following sections as they occur. The TSPA-LA approach to implementing the models for waste package and waste form response during igneous intrusion is based on identification of damage zones. Zone 1 includes all emplacement drifts intruded by the basalt dike, and Zone 2 includes all other emplacement drifts in the repository that are not in Zone 1. This model report will document the following model assessments: (1) Mechanical and thermal impacts of basalt magma intrusion on the invert, waste packages and waste forms of the intersected emplacement drifts of Zone 1. (2) Temperature and pressure trends of basaltic magma intrusion intersecting Zone 1 and their potential effects on waste packages and waste forms in Zone 2 emplacement drifts. (3) Deleterious volatile gases, exsolving from the intruded basalt magma and their potential effects on waste packages of Zone 2 emplacement drifts. (4) Post-intrusive physical
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International Nuclear Information System (INIS)
Raber, E.; Helm, D.; Carpenter, D.; Peifer, D.; Sweeney, J.
1982-01-01
This document was prepared to outline the scope and objectives of the Hazardous Waste Assessment Project (HWAP) at Site 300. This project was initiated in October, 1981, to investigate the existing solid waste landfills in an effort to satisfy regulatory guidelines and assess the potential for ground-water contamination. This involves a site-specific investigation (utilizing geology, hydrology, geophysics and geochemistry) with the goal of developing an effective ground-water quality monitoring network. Initial site reconnaissance work has begun and we report the results, to date, of our geologic hydrogeologic studies. All known solid waste disposal locations are underlain by rocks of either the Late Miocene Neroly Formation or the Cierbo Formation, both of which are dominantly sandstones interbedded with shale and claystone. The existence of a regional confined (artesian) aquifer, as well as a regional water-table aquifer is postulated for Site 300. Preliminary analysis has led to an understanding of directions and depths of regional ground-water flow
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International Nuclear Information System (INIS)
ROGERS, P.M.
2000-01-01
This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) for single-shell tank (SST) farms at the Hanford Site. Evidence indicates that releases at four of the seven SST waste management areas have impacted
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Energy Technology Data Exchange (ETDEWEB)
ROGERS, P.M.
2000-06-01
This document is the master work plan for the Resource Conservation and Recovery Act of 1976 (RCRA) for single-shell tank (SST) farms at the Hanford Site. Evidence indicates that releases at four of the seven SST waste management areas have impacted.
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Radioactive wastes handling facility
International Nuclear Information System (INIS)
Hirose, Emiko; Inaguma, Masahiko; Ozaki, Shigeru; Matsumoto, Kaname.
1997-01-01
There are disposed an area where a conveyor is disposed for separating miscellaneous radioactive solid wastes such as metals, on area for operators which is disposed in the direction vertical to the transferring direction of the conveyor, an area for receiving the radioactive wastes and placing them on the conveyor and an area for collecting the radioactive wastes transferred by the conveyor. Since an operator can conduct handling while wearing a working cloth attached to a partition wall as he wears his ordinary cloth, the operation condition can be improved and the efficiency for the separating work can be improved. When the area for settling conveyors and the area for the operators is depressurized, cruds on the surface of the wastes are not released to the outside and the working clothes can be prevented from being involved. Since the wastes are transferred by the conveyor, the operator's moving range is reduced, poisonous materials are fallen and moved through a sliding way to an area for collecting materials to be separated. Accordingly, the materials to be removed can be accumulated easily. (N.H.)
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2010-07-01
... of 1972, as amended (33 U.S.C. 1401); (b) FWPCA means the Federal Water Pollution Control Act, as... matter of any kind or description, including, but not limited to, dredged material, solid waste, incinerator residue, garbage, sewage, sewage sludge, munitions, radiological, chemical, and biological warfare...
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Study on reducing the generation of general waste
International Nuclear Information System (INIS)
Takahashi, Toshio; Aoki, Isao; Watahiki, Masatoshi
2000-04-01
On August 1999, the Director of Tokai Work proposed an activity regarding recycling and reuse of general waste generated from Tokai Works. The activity was initiated by the Waste Management and Fuel Cycle Research Center, and is now being in progress through out the Tokai Works. In the course of this activity, Plutonium Fuel Center had settled the working Group and the issues related to the waste reductive have been examined. This report collects the problems that became obvious through the survey of existing segregation method, treatment process, and the amount of the waste generation, and accounts for the concrete methodology for the recycling and reuse of general waste. In order to reduce waste, it is necessary to aware of the facing issues and adopt the countermeasures proposed in this report whenever possible. The activity will then leads us to reduce waste generation, which in turn will enable us to make 100% waste recycling possible. (author)
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Solid waste combustion for alpha waste incineration
International Nuclear Information System (INIS)
Orloff, D.I.
1981-02-01
Radioactive waste incinerator development at the Savannah River Laboratory has been augmented by fundamental combustion studies at the University of South Carolina. The objective was to measure and model pyrolysis and combustion rates of typical Savannah River Plant waste materials as a function of incinerator operating conditions. The analytical models developed in this work have been incorporated into a waste burning transient code. The code predicts maximum air requirement and heat energy release as a function of waste type, package size, combustion chamber size, and temperature. Historically, relationships have been determined by direct experiments that did not allow an engineering basis for predicting combustion rates in untested incinerators. The computed combustion rates and burning times agree with measured values in the Savannah River Laboratory pilot (1 lb/hr) and full-scale (12 lb/hr) alpha incinerators for a wide variety of typical waste materials
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International Nuclear Information System (INIS)
Uchiyama, Takafumi; Mitsuhashi, Ishi; Matsumoto, Tetsuo; Morishima, Kayoko; Tanzawa, Tomio
2016-01-01
From the progress of decommissioning project work of Tokyo City University Atomic Energy Research Institute, this paper reports the comparison between the actual amount of the waste generated during dismantlement work at liquid waste treatment facilities and the assessment quantity before starting the dismantlement. The quantity assessment was made on the basis of the installation license application, design specifications, drawings, records, history of use, site investigation results, etc. Since this quantity assessment did not take into account the dismantling contents of reservoir concrete, the assessed quantity of non-radioactive waste (NR waste) did not match the sum of actual NR waste. However, if an actually generated quantity of concrete of radioactive waste was added to the quantity assessment as NR waste, the quantity of actually generated NR waste and that of assessed NR waste were nearly consistent, which verified the validity of this assessment. This method is considered to be able to be utilized in the future quantity assessment of decommissioning work and the like. On the other hand, it was found that the number of drums that were actually stored tended to increase more than the estimated number of drum conversion. In old buildings, it is necessary to take into account the generation of waste other than radioactive materials in the quantity assessment stage and dismantlement stage. (A.O.)
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Introduction to Waste Engineering
DEFF Research Database (Denmark)
Christensen, Thomas Højlund
2011-01-01
Solid waste management as introduced in Chapter 1.1 builds in many ways on engineering. Waste engineering here means the skills and ability to understand quantitatively how a waste management system works in such a detail that waste management can be planned, facilities can be designed and sited......) regional plans for waste management, including (3) the selection of main management technologies and siting of facilities, (4) the design of individual technological units and, for example, (5) the operation of recycling schemes within a municipality. This chapter gives an introduction to waste engineering...
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2011-01-28
... will dispose of the leachate at a publicly owned treatment works or at an industrial waste disposal... classification of listed waste pursuant to Sec. Sec. 261.31 and 261.32. Specifically, in its petition, Gulf West... Waste Management System; Identification and Listing of Hazardous Waste; Proposed Rule AGENCY...
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International Nuclear Information System (INIS)
Abston, J.P.; Burman, S.N.; Jones, D.L.
1995-10-01
The health and safety plan/work plan describes a strategy for characterizing the contents of 172 liquid waste and 33 solid waste drums. It also addresses the control measures that will be taken to (1) prevent or minimize any adverse impact on the environment or personnel safety and health and (2) meet standards that define acceptable management of hazardous and radioactive materials and wastes. When writing this document, the authors considered past experiences, recommendations, and best management practices to minimize possible hazards to human health or the environment from events such as fires, explosions, falls, mechanical hazards, or unplanned releases of hazardous or radioactive materials to air, soil, or surface water
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Radioactive Waste Management Program Activities in Croatia
International Nuclear Information System (INIS)
Matanic, R.
2000-01-01
The concept of radioactive waste management in Croatia comprises three major areas: management of low and intermediate level radioactive waste (LILRW), spent fuel management and decommissioning. All the work regarding radioactive waste management program is coordinated by Hazardous Waste Management Agency (APO) and Croatian Power Utility (HEP) in cooperation with other relevant institutions. Since the majority of work has been done in developing low and intermediate level radioactive waste management program, the paper will focus on this part of radioactive waste management, mainly on issues of site selection and characterization, repository design, safety assessment and public acceptance. A short description of national radioactive waste management infrastructure will also be presented. (author)
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Quality checking of radioactive and hazardous waste
International Nuclear Information System (INIS)
Billington, D.M.; Burgoyne, S.M.J.; Dale, C.J.
1992-01-01
This report describes the work of the HMIP Waste Quality Checking Laboratory (WQCL) for the period September 1989 -August 1991. The WQCL has conducted research and development of procedures for the receipt, sampling and analysis of low level solid radioactive waste (LLW), intermediate level radioactive waste (ILW) and hazardous chemical waste (HW). Operational facilities have been commissioned for quality checking both LLW and HW. Waste quality checking has been completed on LLW packages seized from the UK waste disposal route by HMIP Inspectors. Packages have ranged in size from the 200 litre steel drum to half-height ISO freight container. Development work was continued on methods of sample extraction and radio-chemical analysis for cement encapsulated ILW in the form of magnox, graphite and stainless steel. This work was undertaken on non-radioactive simulants. (author)
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Waste generator services implementation plan
Energy Technology Data Exchange (ETDEWEB)
Mousseau, J.; Magleby, M.; Litus, M.
1998-04-01
Recurring waste management noncompliance problems have spurred a fundamental site-wide process revision to characterize and disposition wastes at the Idaho National Engineering and Environmental Laboratory. The reengineered method, termed Waste Generator Services, will streamline the waste acceptance process and provide waste generators comprehensive waste management services through a single, accountable organization to manage and disposition wastes in a timely, cost-effective, and compliant manner. This report outlines the strategy for implementing Waste Generator Services across the INEEL. It documents the culmination of efforts worked by the LMITCO Environmental Management Compliance Reengineering project team since October 1997. These efforts have included defining problems associated with the INEEL waste management process; identifying commercial best management practices; completing a review of DOE Complex-wide waste management training requirements; and involving others through an Integrated Process Team approach to provide recommendations on process flow, funding/charging mechanisms, and WGS organization. The report defines the work that will be performed by Waste Generator Services, the organization and resources, the waste acceptance process flow, the funding approach, methods for measuring performance, and the implementation schedule and approach. Field deployment will occur first at the Idaho Chemical Processing Plant in June 1998. Beginning in Fiscal Year 1999, Waste Generator Services will be deployed at the other major INEEL facilities in a phased approach, with implementation completed by March 1999.
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Waste generator services implementation plan
International Nuclear Information System (INIS)
Mousseau, J.; Magleby, M.; Litus, M.
1998-04-01
Recurring waste management noncompliance problems have spurred a fundamental site-wide process revision to characterize and disposition wastes at the Idaho National Engineering and Environmental Laboratory. The reengineered method, termed Waste Generator Services, will streamline the waste acceptance process and provide waste generators comprehensive waste management services through a single, accountable organization to manage and disposition wastes in a timely, cost-effective, and compliant manner. This report outlines the strategy for implementing Waste Generator Services across the INEEL. It documents the culmination of efforts worked by the LMITCO Environmental Management Compliance Reengineering project team since October 1997. These efforts have included defining problems associated with the INEEL waste management process; identifying commercial best management practices; completing a review of DOE Complex-wide waste management training requirements; and involving others through an Integrated Process Team approach to provide recommendations on process flow, funding/charging mechanisms, and WGS organization. The report defines the work that will be performed by Waste Generator Services, the organization and resources, the waste acceptance process flow, the funding approach, methods for measuring performance, and the implementation schedule and approach. Field deployment will occur first at the Idaho Chemical Processing Plant in June 1998. Beginning in Fiscal Year 1999, Waste Generator Services will be deployed at the other major INEEL facilities in a phased approach, with implementation completed by March 1999
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Mechanical compaction of Waste Isolation Pilot Plant simulated waste
International Nuclear Information System (INIS)
Butcher, B.M.; Thompson, T.W.; VanBuskirk, R.G.; Patti, N.C.
1991-06-01
The investigation described in this report acquired experimental information about how materials simulating transuranic (TRU) waste compact under axial compressive stress, and used these data to define a model for use in the Waste Isolation Pilot Plant (WIPP) disposal room analyses. The first step was to determine compaction curves for various simultant materials characteristic of TRU waste. Stress-volume compaction curves for various combinations of these materials were than derived to represent the combustible, metallic, and sludge waste categories. Prediction of compaction response in this manner is considered essential for the WIPP program because of the difficulties inherent in working with real (radioactive) waste. Next, full-sized 55-gallon drums of simulated combustible, metallic, and sludge waste were axially compacted. These results provided data that can be directly applied to room consolidation and data for comparison with the predictions obtained in Part 1 of the investigation. Compaction curves, which represent the combustible, metallic, and sludge waste categories, were determined, and a curve for the averaged waste inventory of the entire repository was derived. 9 refs., 31 figs., 12 tabs
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Waste Management Program management plan. Revision 1
International Nuclear Information System (INIS)
1997-02-01
As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management's objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL
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CAN WE CONSIDER WASTES GENERATED DURING RADIOIMMUNOASSAYS AS A RADIOACTIVE WASTE?
Directory of Open Access Journals (Sweden)
V. V. Shapilov
2010-01-01
Full Text Available The work presents issues of the radiation protection provision for the management of radioactive waste produced by the radioimmunological analysis with the use of 125I marker, calculated and experimental data on radioactive waste specific activities are analyzed.
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Bondareva, L.; Zakharov, Yu; Goudov, A.
2017-04-01
The paper is dedicated to the mathematical model of slurry wastewater treatment and disposal in a flooded mine working. The goal of the research is to develop and analyze the mathematical model of suspended impurities flow and distribution. Impurity sedimentation model is under consideration. Due to the sediment compaction problem solution domain can be modified. The model allows making a forecast whether volley emission is possible. Numerical simulation results for “Kolchuginskaya” coal mine presented. Impurity concentration diagrams in outflow corresponding to the real full-scale data obtained. Safely operation time mine workings like a wastewater treatment facility are estimated. The carried out calculations demonstrate that the method of industrial wastewater treatment in flooded waste mine workings can be put into practice but it is very important to observe all the processes going on to avoid volley emission of accumulated impurities.
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Technical area status report for low-level mixed waste final waste forms. Volume 1
Energy Technology Data Exchange (ETDEWEB)
Mayberry, J.L.; DeWitt, L.M. [Science Applications International Corp., Idaho Falls, ID (United States); Darnell, R. [EG and G Idaho, Inc., Idaho Falls, ID (United States)] [and others
1993-08-01
The Final Waste Forms (FWF) Technical Area Status Report (TASR) Working Group, the Vitrification Working Group (WG), and the Performance Standards Working Group were established as subgroups to the FWF Technical Support Group (TSG). The FWF TASR WG is comprised of technical representatives from most of the major DOE sites, the Nuclear Regulatory Commission (NRC), the EPA Office of Solid Waste, and the EPA`s Risk Reduction Engineering Laboratory (RREL). The primary activity of the FWF TASR Working Group was to investigate and report on the current status of FWFs for LLNM in this TASR. The FWF TASR Working Group determined the current status of the development of various waste forms described above by reviewing selected articles and technical reports, summarizing data, and establishing an initial set of FWF characteristics to be used in evaluating candidate FWFS; these characteristics are summarized in Section 2. After an initial review of available information, the FWF TASR Working Group chose to study the following groups of final waste forms: hydraulic cement, sulfur polymer cement, glass, ceramic, and organic binders. The organic binders included polyethylene, bitumen, vinyl ester styrene, epoxy, and urea formaldehyde. Section 3 provides a description of each final waste form. Based on the literature review, the gaps and deficiencies in information were summarized, and conclusions and recommendations were established. The information and data presented in this TASR are intended to assist the FWF Production and Assessment TSG in evaluating the Technical Task Plans (TTPs) submitted to DOE EM-50, and thus provide DOE with the necessary information for their FWF decision-making process. This FWF TASR will also assist the DOE and the MWIP in establishing the most acceptable final waste forms for the various LLMW streams stored at DOE facilities.
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Handbook of hazardous waste management
International Nuclear Information System (INIS)
Metry, A.A.
1980-01-01
The contents of this work are arranged so as to give the reader a detailed understanding of the elements of hazardous waste management. Generalized management concepts are covered in Chapters 1 through 5 which are entitled: Introduction, Regulations Affecting Hazardous Waste Management, Comprehensive Hazardous Waste Management, Control of Hazardous Waste Transportation, and Emergency Hazardous Waste Management. Chapters 6 through 11 deal with treatment concepts and are entitled: General Considerations for Hazardous Waste Management Facilities, Physical Treatment of Hazardous Wastes, Chemical Treatment of Hazardous Wastes, Biological Treatment of Hazardous Wastes, Incineration of Hazardous Wastes, and Hazardous Waste Management of Selected Industries. Chapters 12 through 15 are devoted to ultimate disposal concepts and are entitled: Land Disposal Facilities, Ocean Dumping of Hazardous Wastes, Disposal of Extremely Hazardous Wastes, and Generalized Criteria for Hazardous Waste Management Facilities
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Waste analysis plan for 222-S dangerous and mixed waste storage area
International Nuclear Information System (INIS)
Warwick, G.J.
1994-01-01
The 222-S Laboratory Complex, in the southeast corner of the 200 West Area, consists of the 222-S Laboratory, the 222-SA Standards Laboratory, and several ancillary facilities. Currently, 222-S Laboratory activities are in supporting efforts to characterize the waste stored in the 200 Areas single shell and double shell tanks. Besides this work, the laboratory also provides analytical services for waste-management processing plants, Tank Farms, B Plant, 242-A Evaporator Facility, Plutonium-Uranium Extraction Plant, Plutonium Finishing Plant, Uranium-Oxide Plant, Waste Encapsulation Storage Facility, environmental monitoring and surveillance programs, and activities involving essential materials and research and development. One part of the 222-SA Laboratory prepares nonradioactive standards for the 200 Area laboratories. The other section of the laboratory is used for cold (nonradioactive) process development work and standards preparation. The 219-S Waste Handling Facility has three storage tanks in which liquid acid waste from 222-S can be received, stored temporarily, and neutralized. From this facility, neutralized waste, containing radionuclides, is transferred to the Tank Farms. A 700-gallon sodium-hydroxide supply tank is also located in this facility. This plan provides the methods used to meet the acceptance criteria required by the 204-AR Waste Receiving Facility
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International Nuclear Information System (INIS)
Mann, F.M.
1995-01-01
The statements of work for each activity and task of the Hanford Low-Level Tank Waste Performance Assessment project are given for the fiscal years 1996 through 2001. The end product of this program is approval of a final performance assessment by the Department of Energy in the year 2000
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Federal facilities compliance act waste management
International Nuclear Information System (INIS)
Bowers, J.; Gates-Anderson, D.; Hollister, R.; Painter, S.
1999-01-01
Site Treatment Plans (STPs) developed through the Federal Facilities Compliance Act pose many technical and administrative challenges. Legacy wastes managed under these plans require Land Disposal Restriction (LDR) compliance through treatment and ultimate disposal. Although capacity has been defined for most of the Department of Energy wastes, many waste streams require further characterization and many need additional treatment and handling beyond LDR criteria to be able to dispose of the waste. At Lawrence Livermore National Laboratory (LLNL), the Hazardous Waste Management Division has developed a comprehensive Legacy Waste Program. The program directs work to manage low level and mixed wastes to ensure compliance with nuclear facility rules and its STP. This paper provides a survey of work conducted on these wastes at LLNL. They include commercial waste treatment and disposal, diverse forms of characterization, inventory maintenance and reporting, on-site treatment, and treatability studies. These activities are conducted in an integrated fashion to meet schedules defined in the STP. The processes managing wastes are dynamic due to required integration of administrative, regulatory, and technical concerns spanning the gamut to insure safe proper disposal
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Acoustic Resonance Spectroscopy (ARS) Munition Classification System enhancements. Final report
Energy Technology Data Exchange (ETDEWEB)
Vela, O.A.; Huggard, J.C.
1997-09-18
Acoustic Resonance Spectroscopy (ARS) is a non-destructive evaluation technology developed at the Los Alamos National Laboratory (LANL). This technology has resulted in three generations of instrumentation, funded by the Defense Special Weapons Agency (DSWA), specifically designed for field identification of chemical weapon (CW) munitions. Each generation of ARS instrumentation was developed with a specific user in mind. The ARS1OO was built for use by the U.N. Inspection Teams going into Iraq immediately after the Persian Gulf War. The ARS200 was built for use in the US-Russia Bilateral Chemical Weapons Treaty (the primary users for this system are the US Onsite Inspection Agency (OSIA) and their Russian counterparts). The ARS300 was built with the requirements of the Organization for the Prohibition of Chemical Weapons (OPCW) in mind. Each successive system is an improved version of the previous system based on learning the weaknesses of each and, coincidentally, on the fact that more time was available to do a requirements analysis and the necessary engineering development. The ARS300 is at a level of development that warrants transferring the technology to a commercial vendor. Since LANL will supply the computer software to the selected vendor, it is possible for LANL to continue to improve the decision algorithms, add features where necessary, and adjust the user interface before the final transfer occurs. This paper describes the current system, ARS system enhancements, and software enhancements. Appendices contain the Operations Manual (software Version 3.01), and two earlier reports on enhancements.
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Processing constraints on high-level nuclear waste glasses for Hanford Waste Vitrification Plant
International Nuclear Information System (INIS)
Hrma, P.R.
1993-09-01
The work presented in this paper is a part of a major technology program supported by the U.S. Department of Energy (DOE) in preparation for the planned operation of the Hanford Waste Vitrification Plant (HWVP). Because composition of Hanford waste varies greatly, processability is a major concern for successful vitrification. This paper briefly surveys general aspects of waste glass processability and then discusses their ramifications for specific examples of Hanford waste streams
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The weak link in waste management in tropical Asia? Solid waste collection in Bali
MacRae, Graeme; Rodic-Wiersma, Ljiljana
2015-01-01
This article builds on earlier work that examined waste processing options on the island of Bali, which can be seen as a useful "laboratory" for the study of solid waste management (SWM) problems and solutions in tropical Asia. The research reported here examines the challenges of waste
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EPRI waste processing projects
International Nuclear Information System (INIS)
Shaw, R.A.
1987-01-01
The Electric Power Research Institute (EPRI) manages research for its sponsoring electric utilities in the United States. Research in the area of low level radioactive waste (LLRW) from light water reactors focuses primarily on waste processing within the nuclear power plants, monitoring of the waste packages, and assessments of disposal technologies. Accompanying these areas and complimentary to them is the determination and evaluation of the sources of nuclear power plants radioactive waste. This paper focuses on source characterization of nuclear power plant waste, LLRW processing within nuclear power plants, and the monitoring of these wastes. EPRI's work in waste disposal technology is described in another paper in this proceeding by the same author. 1 reference, 5 figures
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International Nuclear Information System (INIS)
McTaggart, J.; Lott, S.
2009-01-01
The U.S. Department of Energy (DOE) amended the Record of Decision (ROD) for the Waste Management Program: Treatment and Storage of Transuranic Waste to centralize transuranic (TRU) waste characterization/certification from fourteen TRU waste sites. This centralization will allow for treatment, characterization and certification of TRU waste from the fourteen sites, thirteen of which are sites with small quantities of TRU waste, at the Idaho National Laboratory (INL) prior to shipping the waste to the Waste Isolation Pilot Plant (WIPP) for disposal. Centralization of this TRU waste will avoid the cost of building treatment, characterization, certification, and shipping capabilities at each of the small quantity sites that currently do not have existing facilities. Advanced Mixed Waste Treatment Project (AMWTP) and Idaho Nuclear Technology and Engineering Center (INTEC) will provide centralized shipping facilities, to WIPP, for all of the small quantity sites. Hanford, the one large quantity site identified in the ROD, has a large number of waste in containers that are over-packed into larger containers which are inefficient for shipment to and disposal at WIPP. The AMWTP at the INL will reduce the volume of much of the CH waste and make it much more efficient to ship and dispose of at WIPP. In addition, the INTEC has a certified remote handled (RH) TRU waste characterization/certification program at INL to disposition TRU waste from the sites identified in the ROD. (authors)
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The handling and disposal of fusion wastes
International Nuclear Information System (INIS)
Broden, K.; Hultgren, Aa.; Olsson, G.
1985-02-01
The radioactive wastes from fusion reactor operation will include spent components, wastes from repair operations, and decontamination waste. Various disposal routes may be considered depending on i.a. the contents of tritium and of long-lived nuclides, and on national regulations. The management philosophy and disposal technology developed in Sweden for light water reactor wastes has been studied at STUDSVIK during 1983--84 and found to be applicable also to fusion wastes, provided a detritiation stage is included. These studies will continue during 1985 and include experimental work on selected fusion activation nuclides. The work presented is associated to the CEC fusion research programme. Valuable discussions and contacts with people working in this programme at Saclay, Ispra and Garching are deeply appreciated. (author)
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Second law analysis of novel working fluid pairs for waste heat recovery by the Kalina cycle
International Nuclear Information System (INIS)
Eller, Tim; Heberle, Florian; Brüggemann, Dieter
2017-01-01
The organic Rankine cycle (ORC) and the Kalina cycle (KC) are potential thermodynamic concepts for decentralized power generation from industrial waste heat at a temperature level below 500 °C. The aim of this work is to investigate in detail novel zeotropic mixtures as working fluid for the KC and compare to sub- and supercritical ORC based on second law efficiency. Heat source temperature is varied between 200 °C and 400 °C. The results show that second law efficiency of KC can be increased by applying alcohol/alcohol mixtures as working fluid instead of ammonia/water mixtures; especially for heat source temperatures above 250 °C. Efficiency increase is in the range of 16% and 75%. Despite this efficiency improvements, ORC with zeotropic mixtures in sub- and supercritical operation mode proves to be superior to KC in the examined temperature range. Second law efficiency is up to 13% higher than for KC. A maximum second law efficiency of 59.2% is obtained for supercritical ORC with benzene/toluene 36/64 at 400 °C heat source temperature. The higher level of efficiency and the lower complexity of ORC in comparison to KC indicate that ORC with zeotropic mixtures offers the greater potential for waste heat recovery. - Highlights: • Kalina Cycle with novel alcohol mixtures as working fluid is investigated. • Results are compared to ammonia/water-Kalina Cycle and ORC. • Second law efficiency of Kalina Cycle can be increased by novel alcohol mixtures. • Efficiency increase is in the range of 16% and 75%. • ORC with zeotropic mixtures proves to be superior to Kalina Cycle.
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International Nuclear Information System (INIS)
Palmu, Marjatta
2015-01-01
The Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP) community, with over 115 participants in 2014, according to its Vision 2025 (IGD-TP, 2009) aims to proceed to obtaining licences to construct and to safely operate deep geological repositories for spent fuel, high-level waste, and other long-lived radioactive waste in their respective countries. The commitment to Vision 2025 includes developing joint means to facilitate access to expertise and technology, and maintain competencies in the field of geological disposal in Europe. In 2012, IGD-TP launched a Working Group on Competence Maintenance, Education and Training (CMET), as one of its permanent joint activities for addressing its commitment to maintain competencies. In 2013, this permanent organisational working group convened for its first meeting and started working with the support of the IGD-TP Secretariat. The work on competence maintenance within this IGD-TP's working group is first of all focusing on benefiting from and promoting the ECVET approach's application in geological disposal and in future competence building of the community. ECVET approach identifies the LOs that need to be mastered by professionals to carry out their work - starting from the early stages of a waste management programme to running the nuclear waste facilities safely and efficiently. LOs are defined in terms of knowledge, skills and competence (KSC) in ECVET ('attitude' is the corresponding term used by the International Atomic Energy Agency). In their different job functions or tasks the professionals carrying out their work need to master these KSCs at specified European Qualification Framework qualification levels (European Qualification Framework or International Standard Classification for Education according to the job's requirements. The ECVET approach is useful for higher education and continuous professional development, too, not just for vocational education
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International Nuclear Information System (INIS)
Mctaggert, Jerri Lynne; Lott, Sheila; Gadbury, Casey
2009-01-01
The U.S. Department of Energy (DOE) amended the Record of Decision (ROD) for the Waste Management Program: Treatment and Storage ofTransuranic Waste to centralize transuranic (TRU) waste characterization/certification from fourteen TRU waste sites. This centralization will allow for treatment, characterization and certification ofTRU waste from the fourteen sites, thirteen of which are sites with small quantities ofTRU waste, at the Idaho National Laboratory (INL) prior to shipping the waste to the Waste Isolation Pilot Plant (WIPP) for disposal. Centralization ofthis TRU waste will avoid the cost ofbuilding treatment, characterization, certification, and shipping capabilities at each ofthe small quantity sites that currently do not have existing facilities. Advanced Mixed Waste Treatment Project (AMWTP) and Idaho Nuclear Technology and Engineering Center (INTEC) will provide centralized shipping facilities, to WIPP, for all ofthe small quantity sites. Hanford, the one large quantity site identified in the ROD, has a large number ofwaste in containers that are overpacked into larger containers which are inefficient for shipment to and disposal at WIPP. The AMWTP at the INL will reduce the volume ofmuch of the CH waste and make it much more efficient to ship and dispose of at WIPP. In addition, the INTEC has a certified remote handled (RH) TRU waste characterization/certification program at INL to disposition TRU waste from the sites identified in the ROD.
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Andrzejewski, Jan
2017-04-01
After the Second World War, during the Potsdam Conference a decision about demilitarization of Germany was made, and as a consequence, ammunition including chemical warfare agents (CWA) was dumped into the basins of the Baltic Sea. This type of weapon was stored in metal barrels that were under strong influence of electrochemical oxidation, also known as corrosion. Several tens years later, scientists were wondering what consequences for marine ecosystem could a leakage from this weapon bring. Although over 70 years passed since the Second World War, the influence of potential leakage of the CWA has not been properly estimated. Thus, the main goal of this work is to estimate dangerous area caused by potential leakage using the NEMO (Nucleus for European Modelling of the Ocean) ocean model. The NEMO ocean model is developed by the European Consortium including research institutes from France, England and Italy. The first step of this work is to implement the model for the area of the Baltic Sea. It requires generation of horizontal and vertical grid, bathymetry, atmospheric forces and lateral boundary conditions. Implemented model will have to be checked - it means it will have to pass a validation process. The Baltic Sea is one of the best measured sea in the World - as a consequence a lot of data are freely available for researchers. After validation and tuning up the model, implementation of passive tracer is planned. Passive tracer is the prognostic variable that could represent concentration of potential leakage and does not have influence on the density of the model. Based on distribution of the passive tracer, dangerous areas in the locations of dumpsites will be assessed. The research work was funded by the European Union (European Regional Development Fund) under the Interreg Baltic Sea Region Programme 2014-2020, project #R013 DAIMON (Decision Aid for Marine Munitions).
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Waste Management Program management plan. Revision 1
Energy Technology Data Exchange (ETDEWEB)
NONE
1997-02-01
As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management`s objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL.
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Management of radioactive mixed wastes in commercial low-level wastes
International Nuclear Information System (INIS)
Kempf, C.R.; MacKenzie, D.R.; Piciulo, P.L.; Bowerman, B.S.; Siskind, B.
1986-01-01
Potential mixed wastes in commercial low-level wastes have been identified and management options applicable to these wastes have been evaluated. Both the identification and management evaluation have necessarily been based on review of NRC and EPA regulations and recommendations. The underlying intent of both agencies is protection of man and/or environment, but differences may occur in the means by which intent is achieved. Apparent discrepancies, data gaps and unresolved issues that have surfaced during the course of this work are discussed
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International Nuclear Information System (INIS)
Tang, Y.S.; Saling, J.H.
1990-01-01
The purposes of the book are: To create a general awareness of technologies and programs of radioactive waste management. To summarize the current status of such technologies, and to prepare practicing scientists, engineers, administrative personnel, and students for the future demand for a working team in such waste management
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Low-risk alternative waste forms for problematic high-level and long-lived nuclear wastes
International Nuclear Information System (INIS)
Stewart, M.W.A.; Begg, B.D.; Moricca, S.; Day, R.A.
2006-01-01
Full text: The highest cost component the nuclear waste clean up challenge centres on high-level waste (HLW) and consequently the greatest opportunity for cost and schedule savings lies with optimising the approach to HLW cleanup. The waste form is the key component of the immobilisation process. To achieve maximum cost savings and optimum performance the selection of the waste form should be driven by the characteristics of the specific nuclear waste to be immobilised, rather than adopting a single baseline approach. This is particularly true for problematic nuclear wastes that are often not amenable to a single baseline approach. The use of tailored, high-performance, alternative waste forms that include ceramics and glass-ceramics, coupled with mature process technologies offer significant performance improvements and efficiency savings for a nuclear waste cleanup program. It is the waste form that determines how well the waste is locked up (chemical durability), and the number of repository disposal canisters required (waste loading efficiency). The use of alternative waste forms for problematic wastes also lowers the overall risk by providing high performance HLW treatment alternatives. The benefits tailored alternative waste forms bring to the HLW cleanup program will be briefly reviewed with reference to work carried out on the following: The HLW calcines at the Idaho National Laboratory; SYNROC ANSTO has developed a process utilising a glass-ceramic combined with mature hot-isostatic pressing (HIP) technology and has demonstrated this at a waste loading of 80 % and at a 30 kg HIP scale. The use of this technology has recently been estimated to result in a 70 % reduction in waste canisters, compared to the baseline borosilicate glass technology; Actinide-rich waste streams, particularly the work being done by SYNROC ANSTO with Nexia Solutions on the Plutonium-residues wastes at Sellafield in the UK, which if implemented is forecast to result in substantial
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Waste management plan for pipeline construction works: basic guideline for its preparation
Energy Technology Data Exchange (ETDEWEB)
Serricchio, Claudio; Caldas, Flaviana V [Petroleo Brasileiro S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil); Souza, Izabel C.A. de; Araujo, Ronaldo G. de [TELSAN, Rio de Janeiro, RJ (Brazil); Souza, Tania Mara [IMC-SASTE, Sao Paulo,SP (Brazil); Veronez, Fernanda A [Bourscheid, Porto Alegre, RS (Brazil)
2009-07-01
During the stage of implementation of the land pipes enterprise, one of the main environmental aspects to be considered was the creation of solid and liquid waste. To mitigate the possible impacts to the environment, the main adopted mitigate measure was the implementation of a Waste Management Plan - WMP. Thus, the management of waste from pipes construction has the challenge of a great variety of stages and phases for the implementation of pipes and the diversity of local situations related to the topographic and hydro-geologic conditions. Considering the peculiarity of the pipes activities, this article proposes the elaboration of a Basic Guide to be used as reference for the creation of WMP's for similar enterprises, using as foundation the data from the three Gas Pipelines: Cabiunas - Vitoria; Vitoria - Cacimbas and Cacimbas - Catu. After the analysis of the three mentioned enterprises, it was verified that the waste management generated on the building and assembling of the land pipes normally occurs in accord with previous planning, but there's no systematization for the waste to be better recycled and reutilized, thus mitigating their creation. (author)
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Disposal facility for radioactive wastes
International Nuclear Information System (INIS)
Utsunomiya, Toru.
1985-01-01
Purpose: To remove heat generated from radioactive wastes thereby prevent the working circumstances from being worsened in a disposal-facility for radioactive wastes. Constitution: The disposal-facility comprises a plurality of holes dug out into the ground inside a tunnel excavated for the storage of radioactive wastes. After placing radioactive wastes into the shafts, re-filling materials are directly filled with a purpose of reducing the dosage. Further, a plurality of heat pipes are inserted into the holes and embedded within the re-filling materials so as to gather heat from the radioactive wastes. The heat pipes are connected to a heat exchanger disposed within the tunnel. As a result, heating of the solidified radioactive wastes itself or the containing vessel to high temperature can be avoided, as well as thermal degradation of the re-filling materials and the worsening in the working circumstance within the tunnel can be overcome. (Moriyama, K.)
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Monitoring of radioactive wastes
International Nuclear Information System (INIS)
Houriet, J.Ph.
1982-08-01
The estimation of risks presented by final disposal of radioactive wastes depends, among other things, on what is known of their radioisotope content. The first aim of this report is to present the current state of possibilities for measuring (monitoring) radionuclides in wastes. The definition of a global monitoring system in the framework of radioactive waste disposal has to be realized, based on the information presented here, in accordance with the results of work to come and on the inventory of wastes to be stored. Designed for direct measurement of unpackaged wastes and for control of wastes ready to be stored, the system would ultimately make it possible to obtain all adaquate information about their radioisotope content with regard to the required disposal safety. The second aim of this report is to outline the definition of such a global system of monitoring. Designed as a workbase and reference source for future work by the National Cooperative for the Storage of Radioactive Waste on the topic of radioactive waste monitoring, this report describes the current situation in this field. It also makes it possible to draw some preliminary conclusions and to make several recommendations. Centered on the possibilities of current and developing techniques, it makes evident that a global monitoring system should be developed. However, it shows that the monitoring of packaged wastes will be difficult, and should be avoided as far as possible, except for control measurements
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International Nuclear Information System (INIS)
1996-10-01
This report discusses issues related to long time-scale underground disposal of radioactive wastes. The chapters are devoted to the following issues: (1) Post closure issues of underground repositories, e.g., record keeping and markers, public reassurance and prevention of misuse; (2) Optimization of radiation protection by optimizing radioactive waste management, siting analysis, repository design etc.; (3) An interface between nuclear safeguards and radioactive waste management by safeguarding conditioning of spent fuel, during operational phase of repository and post-closure phase of the repository. 31 refs
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International Nuclear Information System (INIS)
Witherspoon, P.A.
1977-01-01
Recent conferences between members of OWI and LBL, and members of the Swedish State Power Board have revealed that an abandoned iron ore mine in Stripa, Sweden, can be used in a very profitable manner for a cooperative work program on the problem of radioactive waste storage in mined caverns. The main thrust of this cooperative work program will be to determine the feasibility of using a mined cavern in hard rock as a permanent repository for high level radioactive materials. The ERDA/OWI program is directed along different lines that complement the Swedish program. Seven tasks are involved as follows: Task 1 will investigate over a two-year period the temperature effects in the granite rock mass at Stripa using a full scale electric heater that simulates the energy output of radioactive waste canisters. Task 2 will determine the long term effect of waste heat in a fractured rock mass. Task 3 will assess the fracture hydrology in the Stripa mine. Task 4 will involve geophysical measurements to determine the locations of the fracture system in the granite rock mass. Task 5 is a laboratory investigation on the measurement of rock properties that are urgently needed in the overall problem of evaluating repository sites in the U.S. Task 6 will involve a method of measuring the gross seepage rate in the low permeability granitic rocks at Stripa. Task 7 will determine the virgin state of stress in the fractured granite rock mass at Stripa
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International Nuclear Information System (INIS)
Bray, G.R.
1976-01-01
The main emphasis of the work in the area of partitioning transuranic elements from waste has been in the area of high-level liquid waste. But there are ''other-than-high-level wastes'' generated by the back end of the nuclear fuel cycle that are both large in volume and contaminated with significant quantities of transuranic elements. The combined volume of these other wastes is approximately 50 times that of the solidified high-level waste. These other wastes also contain up to 75% of the transuranic elements associated with waste generated by the back end of the fuel cycle. Therefore, any detailed evaluation of partitioning as a viable waste management option must address both high-level wastes and ''other-than-high-level wastes.''
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Hanford Waste Vitrification Plant applied technology plan
International Nuclear Information System (INIS)
Kruger, O.L.
1990-09-01
This Applied Technology Plan describes the process development, verification testing, equipment adaptation, and waste form qualification technical issues and plans for resolution to support the design, permitting, and operation of the Hanford Waste Vitrification Plant. The scope of this Plan includes work to be performed by the research and development contractor, Pacific Northwest Laboratory, other organizations within Westinghouse Hanford Company, universities and companies with glass technology expertise, and other US Department of Energy sites. All work described in this Plan is funded by the Hanford Waste Vitrification Plant Project and the relationship of this Plan to other waste management documents and issues is provided for background information. Work to performed under this Plan is divided into major areas that establish a reference process, develop an acceptable glass composition envelope, and demonstrate feed processing and glass production for the range of Hanford Waste Vitrification Plant feeds. Included in this work is the evaluation and verification testing of equipment and technology obtained from the Defense Waste Processing Facility, the West Valley Demonstration Project, foreign countries, and the Hanford Site. Development and verification of product and process models and other data needed for waste form qualification documentation are also included in this Plan. 21 refs., 4 figs., 33 tabs
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Healthcare liquid waste management.
Sharma, D R; Pradhan, B; Pathak, R P; Shrestha, S C
2010-04-01
The management of healthcare liquid waste is an overlooked problem in Nepal with stern repercussions in terms of damaging the environment and affecting the health of people. This study was carried out to explore the healthcare liquid waste management practices in Kathmandu based central hospitals of Nepal. A descriptive prospective study was conducted in 10 central hospitals of Kathmandu during the period of May to December 2008. Primary data were collected through interview, observation and microbiology laboratory works and secondary data were collected by records review. For microbiological laboratory works,waste water specimens cultured for the enumeration of total viable counts using standard protocols. Evidence of waste management guidelines and committees for the management of healthcare liquid wastes could not be found in any of the studied hospitals. Similarly, total viable counts heavily exceeded the standard heterotrophic plate count (p=0.000) with no significant difference in such counts in hospitals with and without treatment plants (p=0.232). Healthcare liquid waste management practice was not found to be satisfactory. Installation of effluent treatment plants and the development of standards for environmental indicators with effective monitoring, evaluation and strict control via relevant legal frameworks were realized.
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Vieira, Cristina Dutra; Tagliaferri, Thaysa Leite; de Carvalho, Maria Auxiliadora Roque; de Resende-Stoianoff, Maria Aparecida; Holanda, Rodrigo Assuncao; de Magalhães, Thais Furtado Ferreira; Magalhães, Paula Prazeres; Dos Santos, Simone Gonçalves; de Macêdo Farias, Luiz
2018-04-01
Trying to widen the discussion on the risks associated with dental waste, this study proposed to investigate and genetically compare yeast isolates recovered from dental solid waste and waste workers. Three samples were collected from workers' hands, nasal mucosa, and professional clothing (days 0, 30, and 180), and two from dental waste (days 0 and 180). Slide culture, microscopy, antifungal drug susceptibility, intersimple sequence repeat analysis, and amplification and sequencing of internal transcribed spacer regions were performed. Yeast strains were recovered from all waste workers' sites, including professional clothes, and from waste. Antifungal susceptibility testing demonstrated that some yeast recovered from employees and waste exhibited nonsusceptible profiles. The dendrogram demonstrated the presence of three major clusters based on similarity matrix and UPGMA grouping method. Two branches displayed 100% similarity: three strains of Candida guilliermondii isolated from different employees, working in opposite work shifts, and from diverse sites grouped in one part of branch 1 and cluster 3 that included two samples of Candida albicans recovered from waste and the hand of one waste worker. The results suggested the possibility of cross-contamination from dental waste to waste workers and reinforce the need of training programs focused on better waste management routines. © 2017 The Authors. MicrobiologyOpen published by John Wiley & Sons Ltd.
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Glassy slags as novel waste forms for remediating mixed wastes with high metal contents
International Nuclear Information System (INIS)
Feng, X.; Wronkiewicz, D.J.; Bates, J.K.; Brown, N.R.; Buck, E.C.; Gong, M.; Ebert, W.L.
1994-01-01
Argonne National Laboratory (ANL) is developing a glassy slag final waste form for the remediation of low-level radioactive and mixed wastes with high metal contents. This waste form is composed of various crystalline and metal oxide phases embedded in a silicate glass phase. This work indicates that glassy slag shows promise as final waste form because (1) it has similar or better chemical durability than high-level nuclear waste (HLW) glasses, (2) it can incorporate large amounts of metal wastes, (3) it can incorporate waste streams having low contents of flux components (boron and alkalis), (4) it has less stringent processing requirements (e.g., viscosity and electric conductivity) than glass waste forms, (5) its production can require little or no purchased additives, which can result in greater reduction in waste volume and overall treatment costs. By using glassy slag waste forms, minimum additive waste stabilization approach can be applied to a much wider range of waste streams than those amenable only to glass waste forms
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International Nuclear Information System (INIS)
Tsoulfanidis, N.
1991-01-01
The management of radioactive waste is a very important part of the nuclear industry. The future of the nuclear power industry depends to a large extent on the successful solution of the perceived or real problems associated with the disposal of both low-level waste (LLW) and high-level waste (HLW). All the activities surrounding the management of radioactive waste are reviewed. The federal government and the individual states are working toward the implementation of the Nuclear Waste Policy Act and the Low-Level Waste Policy Act. The two congressional acts are reviewed and progress made as of early 1990 is presented. Spent-fuel storage and transportation are discussed in detail as are the concepts of repositories for HLW. The status of state compacts for LLW is also discussed. Finally, activities related to the decommissioning of nuclear facilities are also described
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Engineering-Scale Demonstration of DuraLith and Ceramicrete Waste Forms
Energy Technology Data Exchange (ETDEWEB)
Josephson, Gary B.; Westsik, Joseph H.; Pires, Richard P.; Bickford, Jody; Foote, Martin W.
2011-09-23
To support the selection of a waste form for the liquid secondary wastes from the Hanford Waste Immobilization and Treatment Plant, Washington River Protection Solutions (WRPS) has initiated secondary waste form testing on four candidate waste forms. Two of the candidate waste forms have not been developed to scale as the more mature waste forms. This work describes engineering-scale demonstrations conducted on Ceramicrete and DuraLith candidate waste forms. Both candidate waste forms were successfully demonstrated at an engineering scale. A preliminary conceptual design could be prepared for full-scale production of the candidate waste forms. However, both waste forms are still too immature to support a detailed design. Formulations for each candidate waste form need to be developed so that the material has a longer working time after mixing the liquid and solid constituents together. Formulations optimized based on previous lab studies did not have sufficient working time to support large-scale testing. The engineering-scale testing was successfully completed using modified formulations. Further lab development and parametric studies are needed to optimize formulations with adequate working time and assess the effects of changes in raw materials and process parameters on the final product performance. Studies on effects of mixing intensity on the initial set time of the waste forms are also needed.
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International Nuclear Information System (INIS)
Sivapalan Kathiravale; Muhd Noor Muhd Yunus
2010-01-01
We currently live in a world where depletion of resources is beyond control. The call for sustainable development both environmentally and economically is spelt out loud and clear. Hence, the current and future generations must ensure that all resources shall be preserved, fully utilized and well managed. Waste generation has been part and parcel of man kinds pursuit for development, be it in social or economic activities. Municipal Solid Waste (MSW) is an example of socio-economic activities that entails with waste generation. Generation rates of MSW vary according to the economic and social standing of a country. This in return will also affect the management style of the MSW generated. Generally, the higher income countries generated more waste, recycle more and have the money to employ new technology to treat their waste. As for the lower income countries, the waste generated is more organic in nature, which calls for lesser recycling, whereas disposal is by open dumping. The effects of this naturally would mean that in the lower income countries pollution to the water and air is huge as compare to the more developed countries. However on the other hand, does waste alone generate harmful gasses that pollute the world or does manufacturing, transportation and power production, which is rampant in the more industrialized countries contributing more towards pollution? This subject is argumentative and could be discussed at length. However, the environment cannot wait for the population to debate on the above matter. Action needs to be taken in a world where economic power determines the treatment method. Hence, the idea of recovering all 'wealth' in the waste is essential to ensure that even the poorest countries could benefit from all waste management technologies. For this to work, recycling, reuse and recovery of energy is essential in an integrated approach towards waste management. This would also mean that many environmental disasters could be avoided
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Waste management plan for pipeline construction works: basic guideline for its preparation
Energy Technology Data Exchange (ETDEWEB)
Serricchio, Claudio; Caldas, Flaviana V. [Petroleo Brasileiro S.A. (PETROBRAS), Rio de Janeiro, RJ (Brazil); Souza, Izabel C.A. de; Araujo, Ronaldo G. de [TELSAN, Rio de Janeiro, RJ (Brazil); Souza, Tania Mara [IMC-SASTE, Sao Paulo,SP (Brazil); Veronez, Fernanda A. [Bourscheid, Porto Alegre, RS (Brazil)
2009-07-01
During the stage of implementation of the land pipes enterprise, one of the main environmental aspects to be considered was the creation of solid and liquid waste. To mitigate the possible impacts to the environment, the main adopted mitigate measure was the implementation of a Waste Management Plan - WMP. Thus, the management of waste from pipes construction has the challenge of a great variety of stages and phases for the implementation of pipes and the diversity of local situations related to the topographic and hydro-geologic conditions. Considering the peculiarity of the pipes activities, this article proposes the elaboration of a Basic Guide to be used as reference for the creation of WMP's for similar enterprises, using as foundation the data from the three Gas Pipelines: Cabiunas - Vitoria; Vitoria - Cacimbas and Cacimbas - Catu. After the analysis of the three mentioned enterprises, it was verified that the waste management generated on the building and assembling of the land pipes normally occurs in accord with previous planning, but there's no systematization for the waste to be better recycled and reutilized, thus mitigating their creation. (author)
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Making sense: duty hours, work flow, and waste in graduate medical education.
Bush, Roger W; Philibert, Ingrid
2009-12-01
Parsimony, and not industry, is the immediate cause of the increase of capital. Industry, indeed, provides the subject which parsimony accumulates. But whatever industry might acquire, if parsimony did not save and store up, the capital would never be the greater.Adam Smith, The Wealth of Nations, book 2, chapter 31In 2003, the Accreditation Council for Graduate Medical Education implemented resident duty hour limits that included a weekly limit and limits on continuous hours. Recent recommendations for added reductions in resident duty hours have produced concern about concomitant reductions in future graduates' preparedness for independent practice. The current debate about resident hours largely does not consider whether all hours residents spend in the educational and clinical-care environment contribute meaningfully either to residents' learning or to effective patient care. This may distract the community from waste in the current clinical-education model. We propose that use of "lean production" and quality improvement methods may assist teaching institutions in attaining a deeper understanding of work flow and waste. These methods can be used to assign value to patient- and learner-centered activities and outputs and to optimize the competing and synergistic aspects of all desired outcomes to produce the care the Institute of Medicine recommends: safe, effective, efficient, patient-centered, timely, and equitable. Finally, engagement of senior clinical faculty in determining the culture of the care and education system will contribute to an advanced social-learning and care network.
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Biofuels from food processing wastes.
Zhang, Zhanying; O'Hara, Ian M; Mundree, Sagadevan; Gao, Baoyu; Ball, Andrew S; Zhu, Nanwen; Bai, Zhihui; Jin, Bo
2016-04-01
Food processing industry generates substantial high organic wastes along with high energy uses. The recovery of food processing wastes as renewable energy sources represents a sustainable option for the substitution of fossil energy, contributing to the transition of food sector towards a low-carbon economy. This article reviews the latest research progress on biofuel production using food processing wastes. While extensive work on laboratory and pilot-scale biosystems for energy production has been reported, this work presents a review of advances in metabolic pathways, key technical issues and bioengineering outcomes in biofuel production from food processing wastes. Research challenges and further prospects associated with the knowledge advances and technology development of biofuel production are discussed. Copyright © 2016. Published by Elsevier Ltd.
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Croatian radioactive waste management program: Current status
International Nuclear Information System (INIS)
Matanic, R.; Lebegner, J.
2001-01-01
Croatia has a responsibility to develop a radioactive waste management program partly due to co-ownership of Krsko nuclear power plant (Slovenia) and partly because of its own medical and industrial radioactive waste. The total amount of generated radioactive waste in Croatia is stored in temporary storages located at two national research institutes, while radioactive waste from Krsko remains in temporary storage on site. National power utility Hrvatska Elektroprivreda (HEP) and Hazardous Waste Management Agency (APO) coordinate the work regarding decommissioning, spent fuel management and low and intermediate level radioactive waste (LILRW) management in Croatia. Since the majority of work has been done in developing the LILRW management program, the paper focuses on this part of radioactive waste management. Issues of site selection, repository design, safety assessment and public acceptance are being discussed. A short description of the national radioactive waste management infrastructure has also been presented. (author)
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The Hazardous Waste/Mixed Waste Disposal Facility
International Nuclear Information System (INIS)
Bailey, L.L.
1991-01-01
The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy's (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency's (EPA's) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996
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UN Data- Environmental Statistics: Waste
World Wide Human Geography Data Working Group — The Environment Statistics Database contains selected water and waste statistics by country. Statistics on water and waste are based on official statistics supplied...
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UN Data: Environment Statistics: Waste
World Wide Human Geography Data Working Group — The Environment Statistics Database contains selected water and waste statistics by country. Statistics on water and waste are based on official statistics supplied...
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Waste Management Process Improvement Project
International Nuclear Information System (INIS)
Atwood, J.; Borden, G.; Rangel, G. R.
2002-01-01
The Bechtel Hanford-led Environmental Restoration Contractor team's Waste Management Process Improvement Project is working diligently with the U.S. Department of Energy's (DOE) Richland Operations Office to improve the waste management process to meet DOE's need for an efficient, cost-effective program for the management of dangerous, low-level and mixed-low-level waste. Additionally the program must meet all applicable regulatory requirements. The need for improvement was highlighted when a change in the Groundwater/Vadose Zone Integration Project's waste management practices resulted in a larger amount of waste being generated than the waste management organization had been set up to handle
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The development of an on-site container
International Nuclear Information System (INIS)
Glass, R.E.; McAllaster, M.E.; Jones, P.L.; McKinney, A.L.
1992-01-01
Sandia National Laboratories (SNL) has developed a package for the on-site transport of chemical munitions for the US Army. This package was designed to prevent the release of lethal quantities of chemical agents during transportation of munitions to the demilitarization facilities on-site. The packaging prevents auto-ignition of the munitions by limiting the thermal and structural assault on the munitions during an accident. This package, with some modifications to account for contents, may be suitable for the on-site transport of mixed wastes at United States Department of Energy facilities. This paper discusses the design and verification testing of the package. The safety criteria for the package were modeled after the International Atomic Energy Agency (IAEA) hypothetical accident sequence and modified to take credit for operational controls. The modified accident sequence consisted of drop, puncture, and thermal events. The post-accident leak rate was established to prevent harm to an exposed worker. The packaging has a mass of 8600 kg and can accommodate up to 3600 kg of contents. The interior of the package is 188 cm in diameter and 232 cm long. Two sample ports can be used to sample the interior of the package prior to opening the closure and an o-ring test port can be used to determine the leak rates prior to and after transport
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Low-level waste certification plan
International Nuclear Information System (INIS)
Greenhalph, W.O.
1995-01-01
This plan describes the organization and methodology for the certification of solid low-level waste (LLW) and mixed-waste (MW) generated at any of the facilities or major work activities of the Engineered Process Application (EPA) organization. The primary LLW and MW waste generating facility operated by EPA is the 377 Building. This plan does not cover the handling of hazardous or non-regulated waste, though they are mentioned at times for completeness
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Incineration of radioactive waste
International Nuclear Information System (INIS)
Eid, C.
1985-01-01
The incineration process currently seems the most appropriate way to solve the problems encountered by the increasing quantities of low and medium active waste from nuclear power generation waste. Although a large number of incinerators operate in the industry, there is still scope for the improvement of safety, throughput capacity and reduction of secondary waste. This seminar intends to give opportunity to scientists working on the different aspects of incineration to present their most salient results and to discuss the possibilities of making headway in the management of LL/ML radioactive waste. These proceedings include 17 contributions ranging over the subjects: incineration of solid β-γ wastes; incineration of other radwastes; measurement and control of wastes; off-gas filtration and release. (orig./G.J.P.)
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Waste management and enzymatic treatment of Municipal Solid Waste
DEFF Research Database (Denmark)
Jensen, Jacob Wagner
generation for subsequent biogas production. Municipal solid waste (MSW) is produced in large amounts every year in the developed part of the world. The household waste composition varies between geographical areas and between seasons. However the overall content of organic and degradable material is rather......The work carried out during the Ph.D. project is part of the Danish Energy Authority funded research project called PSO REnescience and is focussed on studying the enzymatic hydrolysis and liquefaction of waste biomass. The purpose of studying the liquefaction of waste biomass is uniform slurry...... constant between 50 - 60 % wet weight and therefore holds a potential for bioenergy production. The degradable fraction has positive effects for anaerobic digestion when evaluated to desired parameters of anaerobic digestion plants. Wanted parameters are: 1) high organic content (high volatile solid...
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Enhanced On-Site Waste Management of Plasterboard in Construction Works: A Case Study in Spain
Directory of Open Access Journals (Sweden)
Ana Jiménez-Rivero
2017-03-01
Full Text Available On-site management of construction waste commonly determines its destination. In the case of plasterboard (PB, on-site segregation becomes crucial for closed-loop recycling. However, PB is commonly mixed with other wastes in Spain. In this context, the involvement of stakeholders that can contribute to reversing this current situation is needed. This paper analyzes on-site waste management of PB in Spain through a pilot study of a construction site, with the main objective of identifying best practices to increase waste prevention, waste minimization, and the recyclability of the waste. On-site visits and structured interviews were conducted. The results show five management stages: PB distribution (I; PB installation (II; Construction waste storage at the installation area (III; PB waste segregation at the installation area (IV and PB waste transfer to the PB container and storage (V. The proposed practices refer to each stage and include the merging of Stages III and IV. This measure would avoid the mixing of waste fractions in Stage III, maximizing the recyclability of PB. In addition, two requisites for achieving enhanced management are analyzed: ‘Training and commitment’ and ‘fulfilling the requirements established by the current regulation’. The results show that foremen adopted a more pessimistic attitude than installers towards a joint commitment for waste management. Moreover, not all supervisors valued the importance of a site waste management plan, regulated by the Royal Decree 105/2008 in Spain.
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International Nuclear Information System (INIS)
Kobayashi, Kentarou; Akutu, Shigeru; Sasayama, Yasuo; Nakanishi, Masahiro; Ozone, Takashi; Terunuma, Tomomi; Mogaki, Isao; Aizawa, Syuichi; Sugawara, Hiroyuki
2005-07-01
This document is announced about the task of Waste Management Section of Waste Management Division in 2003. Mainly, our tasks are fractionating, incinerating and storing low active solid waste and storing high active solid waste. In addition, we are performing required correspondence about management program of low level waste. We had treated and stored waste safely according to our plan. As a result, we have achieved following outcomes. (1) We incinerated the combustible low active solid waste that is generated by the operation of Tokai Reprocessing Plant and the recovery operation of incident at Low Active Liquid Waste Asphalt Solidification Facility. Waste of this recovery operation is stored in the 2nd Low Active Liquid Waste Asphalt Solidification Storage Facility. We incinerated 58 ton of wastes. (2) We stored low active solid waste 854 drums that accommodate 200L. According to the time of Low-Level Waste Treatment Facility completion, we will be able to avoid full of storage. (3) We stored high active solid waste of 148 drums that accommodate 200L. For the time being, there is no problem as regards the administration of storage facility. (4) We carried out the management program of low level solid waste according to plan. (author)
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International Nuclear Information System (INIS)
Kobayashi, Kentarou; Isozaki, Kouei; Akutu, Shigeru; Nakanishi, Masahiro; Ozone, Takashi; Terunuma, Tomomi
2004-05-01
This document is announced about the task of Waste Management Section of Waste Management Division in 2004. Mainly, our tasks are fractionating, incinerating and storing low active solid waste and storing high active solid waste. In addition, we are performing required correspondence about management program of low level waste. We had treated and stored waste safely according to our plan. As a result, we have achieved following outcomes. (1) We incinerated the combustible low active solid waste that is generated by the operation of Tokai Reprocessing Plant and the recovery operation of incident at Low Active Liquid Waste Asphalt Solidification Facility. Waste of this recovery operation is stored in the 2nd Low Active Liquid Waste Asphalt Solidification Storage Facility. We incinerated 66.7 ton of wastes. (2) We stored low active solid waste 858 drums that accommodate 200L. According to the time of Low-Level Waste Treatment Facility completion, we will be able to avoid full of storage. (3) We stored high active solid waste of 154 drums that accommodate 200 L. For the time being, there is no problem as regards the administration of storage facility. (4) We carried out the management program of low level solid waste according to plan. (author)
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International Nuclear Information System (INIS)
Shu, Gequn; Zhao, Mingru; Tian, Hua; Huo, Yongzhan; Zhu, Weijie
2016-01-01
Organic Rankine Cycle (ORC) on-board is a solution for vehicles to save energy and reduce emission. Considering the characteristics of waste heat from vehicle, the criterions of the suitable working fluid are very strict. R123 and R245fa have been widely used in companies and labs, however, the difference of their properties under different engine conditions still requires further study. During this research, a series of experiments have been done to compare the performance of these two working fluids, what's more, to determine under which engine conditions they are suitable separately. These experimental comparisons are new and important for the targeting design of ORC for vehicles. The result shows that, considering the difference of thermodynamic properties and the limited cooling capacity on board, R123 shows its advantage for the waste heat recovery at heavy duty, while R245fa is more suitable at light-and-medium duty. These properties make R123 suitable for the ORC designed for long-haul heavy-duty truck, while R245fa is suggested for city bus. The following performance test of R123 for waste heat recovery from heavy-duty diesel engine shows that the maximum fuel consumption improvement can be as much as 2.8%. - Highlights: • R123 is more suitable for heavy duty and steady working condition. • R245fa shows its advantage at light-and-medium duty and varying working condition. • R123 suits better for long-haul heavy-duty truck, while R245fa for city bus. • The maximum fuel consumption improvement is as much as 2.8%.
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Waste Encapsulation and Storage Facility (WESF) Dangerous Waste Training Plan (DWTP)
International Nuclear Information System (INIS)
SIMMONS, F.M.
2000-01-01
This Waste Encapsulation Storage Facility (WESF) Dangerous Waste Training Plan (DWTP) applies to personnel who perform work at, or in support of WESF. The plan, along with the names of personnel, may be given to a regulatory agency inspector upon request. General workers, subcontractors, or visiting personnel who have not been trained in the management of dangerous wastes must be accompanied by an individual who meets the requirements of this training plan. Dangerous waste management includes handling, treatment, storage, and/or disposal of dangerous and/or mixed waste. Dangerous waste management units covered by this plan include: less-than-90-day accumulation area(s); pool cells 1-8 and 12 storage units; and process cells A-G storage units. This training plan describes general requirements, worker categories, and provides course descriptions for operation of the WESF permitted miscellaneous storage units and the Less-than-90-Day Accumulation Areas
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Liquid secondary waste: Waste form formulation and qualification
Energy Technology Data Exchange (ETDEWEB)
Cozzi, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, K. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hill, K. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nichols, R. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
2017-07-31
The Hanford Site Effluent Treatment Facility (ETF) currently treats aqueous waste streams generated during site cleanup activities. When the Hanford Tank Waste Treatment and Immobilization Plant (WTP) begins operations, including Direct Feed Low Activity Waste (DFLAW) vitrification, a liquid secondary waste (LSW) stream from the WTP will need to be treated. The volume of effluent for treatment at the ETF will increase significantly. The powdered salt waste form produced by the ETF will be replaced by a stabilized solidified waste form for disposal in Hanford’s Integrated Disposal Facility (IDF). Washington River Protection Solutions is implementing a Secondary Liquid Waste Immobilization Technology Development Plan to address the technology needs for a waste form and solidification process to treat the increased volume of waste planned for disposal at the IDF. Waste form testing to support this plan is composed of work in the near term to provide data as input to a performance assessment (PA) for Hanford’s IDF. In 2015, three Hanford Liquid Secondary Waste simulants were developed based on existing and projected waste streams. Using these waste simulants, fourteen mixes of Hanford Liquid Secondary Waste were prepared and tested varying the waste simulant, the water-to-dry materials ratio, and the dry materials blend composition.1 In FY16, testing was performed using a simulant of the EMF process condensate blended with the caustic scrubber—from the Low Activity Waste (LAW) melter—, processed through the ETF. The initial EMF-16 simulant will be based on modeling efforts performed to determine the mass balance of the ETF for the DFLAW.2 The compressive strength of all of the mixes exceeded the target of 3.4 MPa (500 psi) to meet the requirements identified as potential IDF Waste Acceptance Criteria in Table 1 of the Secondary Liquid Waste Immobilization Technology Development Plan.3 The hydraulic properties of the waste forms tested (hydraulic conductivity
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International Nuclear Information System (INIS)
Dutton, L.M.C.; Hillis, Z.K.; Roehlig, K.J.
2004-01-01
The paper presents the content and major findings of a project on the ''COMParison of Alternative waste management Strategies for long-lived radioactive wastes'' (COMPAS) carried out within the 5 th framework programme of the European commission. Under the leadership of NNC (UK), the project was carried out by individuals representing waste management organisations from 15 European countries. After having compiled information on the nature and amount of long-lived radioactive waste to be managed, issues influencing the selection of waste management strategies and options, presently adopted national strategies as well as options for the future were addressed. Conclusions concerning key issues for the success or otherwise of strategies and management solutions were drawn. (orig.)
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Waste management bibliography 1979-1981
International Nuclear Information System (INIS)
Oakley, D.T.
1981-10-01
The Los Alamos National Laboratory is conducting a variety of research and development to ensure the safety of storing and treating all types of radioactive wastes. These activities include the assay and sorting of waste, the interaction of waste with the earth, and the treatment of waste to reduce the volume and mobility of radionuclides in waste. The practical lessons learned from safely storing waste at Los Alamos since the mid-1940s are an ingredient in determining the direction of our research. National waste management programs are structured according to categories of waste, for example, high level, low level, mill tailings, and transuranic. In this bibliography publications are listed since 1979 according to the following disciplines to show the relevance of work to more than one category of waste: summary and overview; material science; environmental studies; geochemistry and geology; waste assay; soil/waste interactions shallow land burial; volume reduction and technology development; and nonradioactive wastes
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Current DOE direction in low-level waste management
International Nuclear Information System (INIS)
Wilhite, E.L.; Dolenc, M.R.; Shupe, M.W.; Waldo, L.C.
1989-01-01
The U.S. Department of Energy (DOE) is implementing revised DOE Order 5820.2A Radioactive Waste Management. Chapter III of the revised order provides prescriptive requirements for managing low-level waste and is the subject of this paper. The revised order requires that all DOE low-level radioactive and mixed waste be systematically managed, using an approach that considers the combination of waste management practices used in waste generation reduction, segregation, treatment, packaging, storage, and disposal. The Order defines performance objectives for protecting groundwater, for protecting against intrusion, and for maintaining adequate operational practices. A performance assessment will be required to ensure that waste management operations comply with these performance objectives. DOE implementation of the revised Order includes work in the areas of leach testing, waste stabilization, waste certification, facility monitoring, and management of unique waste streams. This paper summarizes the status of this work and the current direction DOE is taking in managing low-level waste under DOE 5820.2A
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Liquid Radioactive Wastes Treatment: A Review
Directory of Open Access Journals (Sweden)
Yung-Tse Hung
2011-05-01
Full Text Available Radioactive wastes are generated during nuclear fuel cycle operation, production and application of radioisotope in medicine, industry, research, and agriculture, and as a byproduct of natural resource exploitation, which includes mining and processing of ores, combustion of fossil fuels, or production of natural gas and oil. To ensure the protection of human health and the environment from the hazard of these wastes, a planned integrated radioactive waste management practice should be applied. This work is directed to review recent published researches that are concerned with testing and application of different treatment options as a part of the integrated radioactive waste management practice. The main aim from this work is to highlight the scientific community interest in important problems that affect different treatment processes. This review is divided into the following sections: advances in conventional treatment of aqueous radioactive wastes, advances in conventional treatment of organic liquid wastes, and emerged technological options.
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International Nuclear Information System (INIS)
Goguel, Jean; Candes, Pierre; Izabel, Cecile; Autran, Albert; Barthoux, Alain; Baudin, Guy; Devillers, Christian; Habib, Pierre; Lafuma, Jacques; Lefevre, Jean; Peaudecerf, Pierre; Pradel, Jacques; Salle, Claude; Treuil, Michel; Lebrun, Patrick; Tissier, Marie-Solange
1985-06-01
This document is the result of a prospective mission on the long term storage of radioactive wastes containing long-period emitters (wastes of B and C categories), and notably on a definitive storage in deep continental geological formations. After a presentation of hypotheses (brief description of the storage concept, main safety principles, objectives in terms of radiological safety, safety options, time-related considerations), the authors addressed the following issues: safety before closing during the exploitation period, and safety after closure (after backfilling and sealing of all underground cavities). For the first issue, they discuss the impacts of works on safety and thermal effects during exploitation. For the second issue, they discuss the site natural hydro-geological context, the disturbances brought by the storage (access of water to the storage, and return of water into the biosphere), and the influence of external factors (geological phenomena, human intrusion). Then, the authors make recommendations regarding reconnaissance programs and studies for the selection and qualification of a site. They finally propose technical criteria and main recommendations for site selection. Appendices propose a list of hearings, a presentation of the storage concept, a report on the impact of works, a report on the presence of mineralisation in granite massifs, reports on radiological consequences of intrusions in salt formations and in granite massif containing storage of radioactive wastes or vitrified wastes, a report on the characterization of unsteady parts of the French continental construction, a presentation of the evolution of climate and icings, and a study of seismic movements in the case of deep storages
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PROFILE OF PLASTIC WATER BOTTLES WASTES PROCESSING BUSINESS UNIT FOR WASTE PICKERS
Directory of Open Access Journals (Sweden)
Herijanto P.
2017-09-01
Full Text Available Used plastic water bottles waste pickers can be categorized as one of the informal sector’s component. They work for themselves by picking up used water bottles and selling them to the waste collectors. The problem to be solved in this research is How the Most Appropriate Used Plastic Water Bottles Business Model for Waste Pickers Is that enables them to be categorized as formal sector. From the result of the interview with 120 waste pickers, 96 results were qualified to be analyzed. The interview was located in several waste collectors, which were visited by waste pickers at certain hours. The data were analyzed descriptively based on six business aspects. Specifically for production facilities, Quality Function Deployment (QFD and Value Engineering (VE analysis were performed. The results of the analysis indicate that the business is practicable for waste pickers and has the potential to enable them run a formal business sector.
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The concern with the radioactive waste and the reality of the urban waste
International Nuclear Information System (INIS)
Zancheta, Marcio Nestor; Jiurgiu, Paulo Adriano
2009-01-01
One of the greatest present urban challenges, faced by public administrators, legislators and technicians, is the management of urban waste. A significant part of it is still disposed of in an inadequate way that is aggressive to the environment and to society. Initially, this work starts with a brief history of aspects connected to urban waste, then, despite the lack of comprehensive information, quantities generated and associated factors, aspects and impacts referring to landfills, techniques related to the burning process and biological treatments, for specific types of waste, are analyzed. The final destination of almost the whole amount of waste collected worldwide is, also, approached herein. In parallel, after the discovery of radioactivity and its usage in different areas of activities, the destination of the radioactive waste, in a much smaller amount, however potentially much more dangerous, has also been an object of concern that is more in evidence than the problem related to urban waste, due to a strong negative media influence. After the comparison between volumes and impacts which are involved and considering that both represent environmental liability, a more detailed analysis of cases showing risks to the public should be initiated, showing the importance of the adequate management of both wastes and, mainly, the consequent real proportions regarding development, growth and demographic densification. The aim of this work is to analyze the present world situation regarding available information on the involved volumes in the process of urban waste disposal and its environmental impacts in medium and long terms, comparing these data to the same parameters applied to nuclear waste, showing that both activities present inherent risks and relevant impacts. (author)
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Radioactive waste management - a safe solution
International Nuclear Information System (INIS)
1993-01-01
This booklet sets out current United Kingdom government policy regarding radioactive waste management and is aimed at reassuring members of the public concerned about the safety of radioactive wastes. The various disposal or, processing or storage options for low, intermediate and high-level radioactive wastes are explained and sites described, and the work of the Nuclear Industry Radioactive Waste Executive (NIREX) is outlined. (UK)
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Construction waste rises up the agenda.
Moon, David
2010-10-01
Building maintenance and the construction of new healthcare facilities are central to maintaining the NHS's infrastructure, but such work is costly, and subject to intense financial scrutiny. Dr David Moon, programme manager, Clients and Policy, at Government-backed WRAP (the Waste & Resources Action Programme), which works in England, Scotland, Wales, and Northern Ireland, to help businesses and individuals reduce waste, develop sustainable products, and use resources efficiently, outlines the crucial role that NHS Trusts play in securing cost savings through minimising construction waste, as set out in a new WRAP guide.
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Solidification of ion exchange resin wastes in hydraulic cement
International Nuclear Information System (INIS)
Neilson, R.M. Jr.; Kalb, P.; Fuhrmann, M.; Colombo, P.
1982-01-01
Work has been conducted to investigate the solidification of ion exchange resin wastes with portland cements. These efforts have been directed toward the development of acceptable formulations for the solidification of ion exchange resin wastes and the characterization of the resultant waste forms. This paper describes formulation development work and defines acceptable formulations in terms of ternary phase compositional diagrams. The effects of cement type, resin type, resin loading, waste/cement ratio and water/cement ratio are described. The leachability of unsolidified and solidified resin waste forms and its relationship to full-scale waste form behavior is discussed. Gamma irradiation was found to improve waste form integrity, apparently as a result of increased resin crosslinking. Modifications to improve waste form integrity are described. 3 tables
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DEFF Research Database (Denmark)
Edjabou, Vincent Maklawe Essonanawe; Boldrin, Alessio; Scheutz, Charlotte
2015-01-01
Existing legislation mandates that the amount of waste being recycled should be increased. Among others, in its Resource Strategy Plan, the Danish Government decided that at least 60% of food waste generated by the service sector, including in office areas, should be source-sorted and collected...... separately by 2018. To assess the achievability of these targets, source-sorted food waste and residual waste from office areas was collected and weighed on a daily basis during 133 working days. Waste composition analyses were conducted every week to investigate the efficiency of the source-sorting campaign...... and the purity of the source-sorted food waste. The moisture content of source-sorted food waste and residual waste fractions, and potential methane production from source-sorted food waste, was also investigated.Food waste generation equated to 23. ±. 5. kg/employee/year, of which 20. ±. 5. kg...
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Method of controlling radioactive waste processing systems
International Nuclear Information System (INIS)
Mikawa, Hiroji; Sato, Takao.
1981-01-01
Purpose: To minimize the pellet production amount, maximize the working life of a solidifying device and maintaining the mechanical strength of pellets to a predetermined value irrespective of the type and the cycle of occurrence of the secondary waste in the secondary waste solidifying device for radioactive waste processing systems in nuclear power plants. Method: Forecasting periods for the type, production amount and radioactivity level of the secondary wastes are determined in input/output devices connected to a control system and resulted signals are sent to computing elements. The computing elements forecast the production amount of regenerated liquid wastes after predetermined days based on the running conditions of a condensate desalter and the production amounts of filter sludges and liquid resin wastes after predetermined days based on the liquid waste processing amount or the like in a processing device respectively. Then, the mass balance between the type and the amount of the secondary wastes presently stored in a tank are calculated and the composition and concentration for the processing liquid are set so as to obtain predetermined values for the strength of pellets that can be dried to solidify, the working life of the solidifying device itself and the radioactivity level of the pellets. Thereafter, the running conditions for the solidifying device are determined so as to maximize the working life of the solidifying device. (Horiuchi, T.)
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Waste Water Disposal Design And Management I
International Nuclear Information System (INIS)
Yang, Sang Hyeon; Lee, Jung Su
2004-04-01
This book gives descriptions of waste water disposal, design and management, which includes design of waterworks and sewerage facility such as preparatory work and building plan, used waste water disposal facilities, waste water disposal plant and industrial waste water disposal facilities, water use of waste water disposal plant and design of pump and pump facilities such as type and characteristic, selection and plan, screening and grit.
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Iodine waste form summary report (FY 2007)
International Nuclear Information System (INIS)
Krumhansl, James Lee; Nenoff, Tina Maria; McMahon, Kevin A.; Gao, Huizhen; Rajan, Ashwath Natech
2007-01-01
This new program at Sandia is focused on Iodine waste form development for GNEP cycle needs. Our research has a general theme of 'Waste Forms by Design' in which we are focused on silver loaded zeolite waste forms and related metal loaded zeolites that can be validated for chosen GNEP cycle designs. With that theme, we are interested in materials flexibility for iodine feed stream and sequestration material (in a sense, the ability to develop a universal material independent on the waste stream composition). We also are designing the flexibility to work in a variety of repository or storage scenarios. This is possible by studying the structure/property relationship of existing waste forms and optimizing them to our current needs. Furthermore, by understanding the properties of the waste and the storage forms we may be able to predict their long-term behavior and stability. Finally, we are working collaboratively with the Waste Form Development Campaign to ensure materials durability and stability testing
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Disposal and environmental assessment of solid waste and radioactive waste
International Nuclear Information System (INIS)
Tan Chenglong
2000-01-01
Along with the development of economic construction, the industrial and agricultural production, military and scientific activities of human being, large amounts of solid and radioactive wastes have been produced, causing serious pollution of ecologic environments and living space of human being itself. To assess and administer the solid and radioactive wastes in geologic-ecologic environments are duty-bound responsibilities of modern geologists and the focus of recent geo-ecologic work
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Assessment Strategies for Municipal Selective Waste Collection – Regional Waste Management
Directory of Open Access Journals (Sweden)
Agnieszka Boas Berg
2018-01-01
Full Text Available Waste disposal in landfill sites causes a potentialhazard for the human health, as they release substantial amounts of gas, odours and pollutants to the environment. There have been vast reductions in the volume of waste being landfilledin many European countries and a reduction in the number of illegal landfills The European Parliament’s laws obliged the Member States to amend the national waste law; the main objectives of the implemented directives are to create the conditions for the prevention of excessive waste. Directive 2008/98/EC establishes, as a goal for 2020, that waste reuse and recycling reach 50% of the total waste produced. Poland, having joined the European Union, committed itself to implementing many changes related to waste management. The amendment of the law on the maintenance of cleanliness and order in the municipalities imposed new obligations regarding the waste management (WM on the local government and residents. By adopting a municipal waste management system, the selected municipality made all its residents responsible for their waste. However, the fact of introducing changes does not solve the waste problem. The implementation of EU directives and the development of strategic documents such as the National Waste Management Plan (NWMP have made a clear change in the WM approach. One of the changes was the establishment of selective collection of municipal selective waste (MSW, with the issue of collecting the waste by the residents being a priority. This work describes the legal context of selective collection of MSW as one of the most effective means of reducing the amount of waste being landfilled.
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Radioactive waste. Policy and perspective
Energy Technology Data Exchange (ETDEWEB)
Roberts, L E.J. [UKAEA, Harwell. Atomic Energy Research Establishment
1979-01-01
The subject is covered in sections as follows: general introduction (volume of waste arising from 1 GW/(e) energy per year); characteristics of highly active waste (output of some important fission products from an AGR, decay of activity with time for PWR and CFR wastes, toxic potential versus time for magnox and fast reactor wastes, toxic potential of unreprocessed magnox fuel); general principles of waste disposal (incorporation of waste into solid matrices, glass containers); design of stores and repositories (heat dissipation, siting and design, packing materials, size of repositories); the geologic barrier (location of repositories, safety analysis of repositories); the option of ocean disposal; status of work and present programme (vitrification, repository siting and design); conclusions.
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Mixed Waste Management Facility
International Nuclear Information System (INIS)
Brummond, W.; Celeste, J.; Steenhoven, J.
1993-08-01
The DOE has developed a National Mixed Waste Strategic Plan which calls for the construction of 2 to 9 mixed waste treatment centers in the Complex in the near future. LLNL is working to establish an integrated mixed waste technology development and demonstration system facility, the Mixed Waste Management Facility (MWMF), to support the DOE National Mixed Waste Strategic Plan. The MWMF will develop, demonstrate, test, and evaluate incinerator-alternatives which will comply with regulations governing the treatment and disposal of organic mixed wastes. LLNL will provide the DOE with engineering data for design and operation of new technologies which can be implemented in their mixed waste treatment centers. MWMF will operate under real production plant conditions and process samples of real LLNL mixed waste. In addition to the destruction of organic mixed wastes, the development and demonstration will include waste feed preparation, material transport systems, aqueous treatment, off-gas treatment, and final forms, thus making it an integrated ''cradle to grave'' demonstration. Technologies from offsite as well as LLNL's will be tested and evaluated when they are ready for a pilot scale demonstration, according to the needs of the DOE
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Nuclear waste disposal in space
Burns, R. E.; Causey, W. E.; Galloway, W. E.; Nelson, R. W.
1978-01-01
Work on nuclear waste disposal in space conducted by the George C. Marshall Space Flight Center, National Aeronautics and Space Administration, and contractors are reported. From the aggregate studies, it is concluded that space disposal of nuclear waste is technically feasible.
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Identification and characterization of radioactive wastes
International Nuclear Information System (INIS)
RANDRIAMORA, T.H.
2007-01-01
As the goal of the radioactive waste management is to protect human health and the environment, without imposing excessive constraints to the future generations, this work consists with of the identification of the radioactive waste existing in Madagascar, theirs characterizations for their later conditioning and their final storage. In this work, we used a dosimeter GRAETZ X5 C and a portable spectrometer EXPLORANIUM GR 135. These apparatuses have a great advantage at the user level because of their capacity to measure the equivalent dose rate, to identify, search and locate radiocative elements. The establishment of national center for radioactive waste management for the conditioning and the storage of spent sealed sources is the best solution for radioactive waste management in Madagascar. [fr
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Waste volume reduction by spray drying
Energy Technology Data Exchange (ETDEWEB)
Toscano, Rodrigo A.; Tello, Clédola C. O. de, E-mail: Rodrigotoscano1@gmail.com, E-mail: tellocc@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)
2017-07-01
The operation of nuclear facilities generates liquid wastes which require treatment to control the chemical compounds and removal of radioactive contaminants. These wastes can come from the cooling of the primary reactor system, from the reactor pool decontamination, washing of contaminated clothing, among others. The ion exchange resin constitutes the largest fraction of this waste, classified as low and intermediate level of radiation. According to CNEN Standard 8.01, the minimization of the volume and activity of the radioactive waste generated in the operation of a nuclear installation, radiative installation, industrial mining installation or radioactive waste deposit should be ensured. In addition, one of the acceptance criteria for wastes in repositories required by CNEN NN 6.09 is that it be solid or solidified. Thus, these wastes must be reduced in volume and solidified to meet the standards and the safety of the population and the environment. The objective of this work is to find a solution that associates the least generation of packaged waste and the acceptance criteria of waste for the deposition in the national repository. This work presents a proposal of reduction of the volume of the liquid wastes generated by nuclear facilities by drying by for reduction of volume for a greater incorporation of wastes in cement. Using spray dryer, an 18% reduction in the production of cemented waste products was observed in relation to the method currently used with compressive strength measurement above the standard, and it is believed that this value may increase in future tests. (author)
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Waste volume reduction by spray drying
International Nuclear Information System (INIS)
Toscano, Rodrigo A.; Tello, Clédola C. O. de
2017-01-01
The operation of nuclear facilities generates liquid wastes which require treatment to control the chemical compounds and removal of radioactive contaminants. These wastes can come from the cooling of the primary reactor system, from the reactor pool decontamination, washing of contaminated clothing, among others. The ion exchange resin constitutes the largest fraction of this waste, classified as low and intermediate level of radiation. According to CNEN Standard 8.01, the minimization of the volume and activity of the radioactive waste generated in the operation of a nuclear installation, radiative installation, industrial mining installation or radioactive waste deposit should be ensured. In addition, one of the acceptance criteria for wastes in repositories required by CNEN NN 6.09 is that it be solid or solidified. Thus, these wastes must be reduced in volume and solidified to meet the standards and the safety of the population and the environment. The objective of this work is to find a solution that associates the least generation of packaged waste and the acceptance criteria of waste for the deposition in the national repository. This work presents a proposal of reduction of the volume of the liquid wastes generated by nuclear facilities by drying by for reduction of volume for a greater incorporation of wastes in cement. Using spray dryer, an 18% reduction in the production of cemented waste products was observed in relation to the method currently used with compressive strength measurement above the standard, and it is believed that this value may increase in future tests. (author)
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International Nuclear Information System (INIS)
1992-10-01
This progress report covers the state and results of the projects undertaken in the area of waste management. In particular, results in the area of decommissioning and retreat of nuclear installations are documented. Furthermore, measures designed to increase environmental compatibility are taken into account. Experimental results regarding the concept, planning, construction, operation, decommissioning and post-operational phase of a repository or underground disposal of hazardous wastes are also described. Lists of formalized interim reports and research institutions involved are attached. (DG) [de
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Long-term management plan INEL transuranic waste
International Nuclear Information System (INIS)
McKinney, J.D.
1978-12-01
The Idaho National Engineering Laboratory stores large quantities of transuranic-contaminated waste at its Radioactive Waste Management Complex. This report presents a 10-year plan for management of this transuranic waste and includes descriptions of projects involving nuclear waste storage, retrieval, processing, systems analysis, and environmental science. Detailed project schedules and work breakdown charts are provided to give the reader a clear view of transuranic waste management objectives
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Interim report to the Nuclear Regulatory Commission on radioactive waste classification
International Nuclear Information System (INIS)
King, W.C.; Cohen, J.J.
1977-01-01
The Lawrence Livermore Laboratory assisted the Nuclear Regulatory Commission in the development of a radioactive waste classification system that will satisfy technical, environmental, and societal concerns. This is an interim report to the NRC on work accomplished to date. It describes a proposed waste-classification system that is based on the final disposition of waste material. The system consists of three classes of radioactive waste. The classification of any radioactive waste will depend primarily on its hazard potential. Other characteristics such as longevity (half-size) will be considered also. The levels of hazard that differentiate the three classes of radioactive waste will be determined by ongoing work. This report describes other work to be completed before a suitable radioactive waste-classificaion system is established
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Glass Ceramic Waste Forms for Combined CS+LN+TM Fission Products Waste Streams
International Nuclear Information System (INIS)
Crum, Jarrod V.; Turo, Laura A.; Riley, Brian J.; Tang, Ming; Kossoy, Anna; Sickafus, Kurt E.
2010-01-01
In this study, glass ceramics were explored as an alternative waste form for glass, the current baseline, to be used for immobilizing alkaline/alkaline earth + lanthanide (CS+LN) or CS+LN+transition metal (TM) fission-product waste streams generated by a uranium extraction (UREX+) aqueous separations type process. Results from past work on a glass waste form for the combined CS+LN waste streams showed that as waste loading increased, large fractions of crystalline phases precipitated upon slow cooling.(1) The crystalline phases had no noticeable impact on the waste form performance by the 7-day product consistency test (PCT). These results point towards the development of a glass ceramic waste form for treating CS+LN or CS+LN+TM combined waste streams. Three main benefits for exploring glass ceramics are: (1) Glass ceramics offer increased solubility of troublesome components in crystalline phases as compared to glass, leading to increased waste loading; (2) The crystalline network formed in the glass ceramic results in higher heat tolerance than glass; and (3) These glass ceramics are designed to be processed by the same melter technology as the current baseline glass waste form. It will only require adding controlled canister cooling for crystallization into a glass ceramic waste form. Highly annealed waste form (essentially crack free) with up to 50X lower surface area than a typical High-Level Waste (HLW) glass canister. Lower surface area translates directly into increased durability. This was the first full year of exploring glass ceramics for the Option 1 and 2 combined waste stream options. This work has shown that dramatic increases in waste loading are achievable by designing a glass ceramic waste form as an alternative to glass. Table S1 shows the upper limits for heat, waste loading (based on solubility), and the decay time needed before treatment can occur for glass and glass ceramic waste forms. The improvements are significant for both combined waste
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Glass Ceramic Waste Forms for Combined CS+LN+TM Fission Products Waste Streams
Energy Technology Data Exchange (ETDEWEB)
Crum, Jarrod V.; Turo, Laura A.; Riley, Brian J.; Tang, Ming; Kossoy, Anna; Sickafus, Kurt E.
2010-09-23
In this study, glass ceramics were explored as an alternative waste form for glass, the current baseline, to be used for immobilizing alkaline/alkaline earth + lanthanide (CS+LN) or CS+LN+transition metal (TM) fission-product waste streams generated by a uranium extraction (UREX+) aqueous separations type process. Results from past work on a glass waste form for the combined CS+LN waste streams showed that as waste loading increased, large fractions of crystalline phases precipitated upon slow cooling.[1] The crystalline phases had no noticeable impact on the waste form performance by the 7-day product consistency test (PCT). These results point towards the development of a glass ceramic waste form for treating CS+LN or CS+LN+TM combined waste streams. Three main benefits for exploring glass ceramics are: (1) Glass ceramics offer increased solubility of troublesome components in crystalline phases as compared to glass, leading to increased waste loading; (2) The crystalline network formed in the glass ceramic results in higher heat tolerance than glass; and (3) These glass ceramics are designed to be processed by the same melter technology as the current baseline glass waste form. It will only require adding controlled canister cooling for crystallization into a glass ceramic waste form. Highly annealed waste form (essentially crack free) with up to 50X lower surface area than a typical High-Level Waste (HLW) glass canister. Lower surface area translates directly into increased durability. This was the first full year of exploring glass ceramics for the Option 1 and 2 combined waste stream options. This work has shown that dramatic increases in waste loading are achievable by designing a glass ceramic waste form as an alternative to glass. Table S1 shows the upper limits for heat, waste loading (based on solubility), and the decay time needed before treatment can occur for glass and glass ceramic waste forms. The improvements are significant for both combined waste
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International Nuclear Information System (INIS)
Cheung, H.; Jackson, D.D.; Revelli, M.A.
1981-07-01
Waste form dissolution studies and preliminary performance analyses were carried out to contribute a part of the data needed for the selection of a waste form for the disposal of Savannah River Plant defense waste in a deep geologic repository. The first portion of this work provides descriptions of the chemical interactions between the waste form and the geologic environment. We reviewed critically the dissolution/leaching data for borosilicate glass and SYNROC. Both chemical kinetic and thermodynamic models were developed to describe the dissolution process of these candidate waste forms so as to establish a fundamental basis for interpretation of experimental data and to provide directions for future experiments. The complementary second portion of this work is an assessment of the impacts of alternate waste forms upon the consequences of disposal in various proposed geological media. Employing systems analysis methodology, we began to evaluate the performance of a generic waste form for the case of a high risk scenario for a bedded salt repository. Results of sensitivity analysis, uncertainty analyses, and sensitivity to uncertainty analysis are presented
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Suggestions on R and D work of high-level radioactive waste disposal in China
International Nuclear Information System (INIS)
Xu Guoqing
2012-01-01
The difference between repository and generic underground facilities is described. Some differences and similarities of site selection between the low and medium radioactive waste disposal, nuclear power station and high-level radioactive waste repository are also discussed here. We trend to extremely emphasize the safety of high-level radioactive waste disposal because of high toxicity, long half-life and long safety disposal period of this kind of radioactive wastes; because radioactive waste in the repository is of high specific activities and buried in depth, it would be difficult to meddle with its safety. In case of repository system being destroyed, the author considers that in the stages of regional and area site selection, the first task is to investigate regional tectonic stability. Some problems about disposal options and others are also discussed in this paper. (author)
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Radioactive waste management research at CEGB Berkeley nuclear laboratories
International Nuclear Information System (INIS)
Bradbury, D.
1988-01-01
The CEGB is the major electric utility in the United Kingdom. This paper discusses how, at the research laboratories at Berkeley (BNL), several programs of work are currently taking place in the radioactive waste management area. The theme running through all this work is the safe isolation of radionuclides from the environment. Normally this means disposal of waste in solid form, but it may also be desirable to segregate and release nonradioactive material from the waste to reduce volume or improve the solid waste characteristics (e.g., the release of liquid or gaseous effluents after treatment to convert the radioactivity to solid form). The fuel cycle and radioactive waste section at BNL has a research program into these aspects for wastes arising from the operation or decommissioning of power stations. The work is done both in-house and on contract, with primarily the UKAEA
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The Construction Solid Waste Minimization Practices among Malaysian Contractors
Directory of Open Access Journals (Sweden)
Che Ahmad A.
2014-01-01
Full Text Available The function of minimization of construction solid waste is to reduce or eliminates the adverse impacts on the environment and to human health. Due to the increase of population that leads to rapid development, there are possibilities of construction solid waste to be increased shortly from the construction works, demolition or renovation works. Materials such as wood, concrete, paint, brick, roofing, tiles, plastic and any other materials would contribute problem involving construction solid waste. Therefore, the proper waste minimization is needed to control the quantity of construction solid waste produced. This paper identifies the type of construction solid waste produced and discusses the waste minimization practice by the contractors at construction sites in Selangor, Kuala Lumpur and Putrajaya, Malaysia.
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Materials for Waste Incinerators and Biomass Plants
DEFF Research Database (Denmark)
Rademakers, P.; Grossmann, G.; Karlsson, A.
1998-01-01
This paper reviews the projects of the sub-package on waste incineration and biomass firing carried out within COST 501 Round III, Work Package 13.......This paper reviews the projects of the sub-package on waste incineration and biomass firing carried out within COST 501 Round III, Work Package 13....
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NWTS waste package program plan. Volume II. Program logic networks
International Nuclear Information System (INIS)
1981-10-01
This document describes the work planned for developing the technology to design, test and produce packages used for the long-term isolation of nuclear waste in deep geologic repositories. Waste forms considered include spent fuel and high-level waste. The testing and selection effort for barrier materials for radionuclide containment is described. The NWTS waste package program is a design-driven effort; waste package conceptual designs are used as input for preliminary designs, which are upgraded to a final design as materials and testing data become available. Performance assessment models are developed and validated. Milestones and a detailed schedule are given for the waste package development effort. Program logic networks defining work flow, interfaces among the NWTS Projects, and interrelationships of specific activities are presented. Detailed work elements are provided for the Waste Package Program Plan subtasks - design and development, waste form, barrier materials, and performance evaluation - for salt and basalt, host rocks for which the state of waste package knowledge and the corresponding data base are advanced
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Waste to Want: Polymer nanocomposites using nanoclays extracted from Oil based drilling mud waste
International Nuclear Information System (INIS)
Adegbotolu, Urenna V; Njuguna, James; Pollard, Pat; Yates, Kyari
2014-01-01
Due to the European Union (EU) waste frame work directive (WFD), legislations have been endorsed in EU member states such as UK for the Recycling of wastes with a vision to prevent and reduce landfilling of waste. Spent oil based drilling mud (drilling fluid) is a waste from the Oil and Gas industry with great potentials for recycling after appropriate clean-up and treatment processes. This research is the novel application of nanoclays extracted from spent oil based drilling mud (drilling fluid) clean-up as nanofiller in the manufacture of nanocomposite materials. Research and initial experiments have been undertaken which investigate the suitability of Polyamide 6 (PA6) as potential polymer of interest. SEM and EDAX were used to ascertain morphological and elemental characteristics of the nanofiller. ICPOES has been used to ascertain the metal concentration of the untreated nanofiller to be treated (by oil and heavy metal extraction) before the production of nanocomposite materials. The challenges faced and future works are also discussed
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OPG Western Waste Management Facility
Energy Technology Data Exchange (ETDEWEB)
Julian, J. [Ontario Power Generation, Western Waste Management Facility, Tiverton, ON (Canada)
2011-07-01
The Ontario Power Generation (OPG) Western Waste Management Facility (WWMF) uses a computer based Supervisory Control and Data Acquisition (SCADA) system to monitor its facility, and control essential equipment. In 2007 the WWMF Low and Intermediate Level Waste (L&ILW) technical support section conducted a review of outstanding corrective maintenance work. Technical support divided all work on a system by system basis. One system under review was the Waste Volume Reduction Building (WVRB) control room SCADA system. Technical support worked with control maintenance staff to assess all outstanding work orders on the SCADA system. The assessment identified several deficiencies in the SCADA system. Technical support developed a corrective action plan for the SCADA system deficiencies, and in February of 2008 developed an engineering change package to correct the observed deficiencies. OPG Nuclear Waste Engineering approved the change package and the WVRB Control Room Upgrades construction project started in January of 2009. The WVRB control room upgrades construction work was completed in February of 2009. This paper provides the following information regarding the WWMF SCADA system and the 2009 WVRB Control Room Upgrades Project: A high-level explanation of SCADA system technology, and the various SCADA system components installed in the WVRB; A description of the state of the WVRB SCADA system during the work order assessment, identifying all deficiencies; A description of the new design package; A description of the construction project; and, A list of lessons learned during construction and commissioning, and a path forward for future upgrades. (author)
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OPG Western Waste Management Facility
International Nuclear Information System (INIS)
Julian, J.
2011-01-01
The Ontario Power Generation (OPG) Western Waste Management Facility (WWMF) uses a computer based Supervisory Control and Data Acquisition (SCADA) system to monitor its facility, and control essential equipment. In 2007 the WWMF Low and Intermediate Level Waste (L&ILW) technical support section conducted a review of outstanding corrective maintenance work. Technical support divided all work on a system by system basis. One system under review was the Waste Volume Reduction Building (WVRB) control room SCADA system. Technical support worked with control maintenance staff to assess all outstanding work orders on the SCADA system. The assessment identified several deficiencies in the SCADA system. Technical support developed a corrective action plan for the SCADA system deficiencies, and in February of 2008 developed an engineering change package to correct the observed deficiencies. OPG Nuclear Waste Engineering approved the change package and the WVRB Control Room Upgrades construction project started in January of 2009. The WVRB control room upgrades construction work was completed in February of 2009. This paper provides the following information regarding the WWMF SCADA system and the 2009 WVRB Control Room Upgrades Project: A high-level explanation of SCADA system technology, and the various SCADA system components installed in the WVRB; A description of the state of the WVRB SCADA system during the work order assessment, identifying all deficiencies; A description of the new design package; A description of the construction project; and, A list of lessons learned during construction and commissioning, and a path forward for future upgrades. (author)
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International Nuclear Information System (INIS)
Fujikawa, Yoko
2012-01-01
A large amount of radioactive substances were discharge by the catastrophe of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company. From the analysis of the dynamic state of radioactive substances in the environment, the radioactive cesium in the land and freshwater environment is distributed much in soil and freshwater sediment (solid phase) rather than in aqueous phase, even though the distribution depends on the composition of liquid phase water and adsorption objects. From this fact, the problem of radioactive cesium in the living environment can be summarized in the problem of solid system disaster waste in the end, such as soil, sediment, sludge, and waste. As for the current situation of disaster waste, this paper introduces the present state of disaster waste, in which treatment operations are not smoothly proceeding due to the large amount of waste, and difficulty in the classification work of waste and incineration treatment work. Regarding the wide-area treatment measures, there are various problems such that some municipalities are cooperative and some municipalities are hesitant about the acceptance of waste with radioactive contamination. As an example, this paper introduces the reviewing process and reference information in Osaka Prefecture regarding the acceptance of waste. (O.A.)
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International Nuclear Information System (INIS)
M. Gross
2006-01-01
The overall objective of the work scope covered by this technical work plan (TWP) is to develop new damage abstractions for the seismic scenario class in total system performance assessment (TSPA). The new abstractions will be based on a new set of waste package and drip shield damage calculations in response to vibratory ground motion and fault displacement. The new damage calculations, which are collectively referred to as damage models in this TWP, are required to represent recent changes in waste form packaging and in the regulatory time frame. The new damage models also respond to comments from the Independent Validation Review Team (IVRT) postvalidation review of the draft TSPA model regarding performance of the drip shield and to an Additional Information Need (AIN) from the U.S. Nuclear Regulatory Commission (NRC)
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Energy Technology Data Exchange (ETDEWEB)
M. Gross
2006-12-08
The overall objective of the work scope covered by this technical work plan (TWP) is to develop new damage abstractions for the seismic scenario class in total system performance assessment (TSPA). The new abstractions will be based on a new set of waste package and drip shield damage calculations in response to vibratory ground motion and fault displacement. The new damage calculations, which are collectively referred to as damage models in this TWP, are required to represent recent changes in waste form packaging and in the regulatory time frame. The new damage models also respond to comments from the Independent Validation Review Team (IVRT) postvalidation review of the draft TSPA model regarding performance of the drip shield and to an Additional Information Need (AIN) from the U.S. Nuclear Regulatory Commission (NRC).
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Energy Technology Data Exchange (ETDEWEB)
Cantrell, Kirk J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westsik, Joseph H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Serne, R Jeffrey [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Um, Wooyong [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Cozzi, Alex D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
2016-05-16
A review of the most up-to-date and relevant data currently available was conducted to develop a set of recommended values for use in the Integrated Disposal Facility (IDF) performance assessment (PA) to model contaminant release from a cementitious waste form for aqueous wastes treated at the Hanford Effluent Treatment Facility (ETF). This data package relies primarily upon recent data collected on Cast Stone formulations fabricated with simulants of low-activity waste (LAW) and liquid secondary wastes expected to be produced at Hanford. These data were supplemented, when necessary, with data developed for saltstone (a similar grout waste form used at the Savannah River Site). Work is currently underway to collect data on cementitious waste forms that are similar to Cast Stone and saltstone but are tailored to the characteristics of ETF-treated liquid secondary wastes. Recommended values for key parameters to conduct PA modeling of contaminant release from ETF-treated liquid waste are provided.
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Waste bituminization system in CDTN
International Nuclear Information System (INIS)
Guzella, M.F.R.; Miaw, S.T.W.
1990-01-01
Experimental works on low level waste bituminization have been developed at the Radioactive Waste Treatment Division of CDTN. A small scale bitumen extruder (1 kg/h) similar to the Angra II one is in operation. Some types of Brazilian bitumen have been selected and incorporation experiments with different types of waste were carried out; the operating conditions have been defined and the final product properties investigated. (author) [pt
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Aspects of nuclear waste management
International Nuclear Information System (INIS)
Moberg, L.
1990-10-01
Six areas of concern in nuclear waste management have been dealt with in a four-year Nordic research programme. They include work in two international projects, Hydrocoin dealing with modelling of groundwater flow in crystalline rock, and Biomovs, concerned with biosphere models. Geologic questions of importance to the prediction of future behaviour are examined. Waste quantities from the decommissioning of nuclear power stations are estimated, and total amounts of waste to be transported in the Nordic countries are evaluated. Waste amounts from a hypothetical reactor accident are also calculated. (au)
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International Nuclear Information System (INIS)
Burbank, D.A.; Weingardt, K.M.
1993-01-01
A testing program has been conducted by the Westinghouse Hanford Co. to confirm the baseline waste form selection for use in Waste Receiving and Processing (WRAP) Module 2A. WRAP Module 2A will provide treatment required to properly dispose of containerized contact-handled, mixed low-level waste at the US DOE Hanford Site in south-central Washington State. Solidification/stabilization has been chosen as the appropriate treatment for this waste. This work is intended to test cement-based and thermosetting polymer solidification media to confirm the baseline technologies selected for WRAP Module 2A. Screening tests were performed using the major chemical constituent of each waste type to measure the gross compatibility with the immobilization media and to determine formulations for more detailed testing. Surrogate wastes representing each of the eight waste types were prepared for testing. Surrogates for polymer testing were sent to a vendor commissioned for that portion of the test work. Surrogates for the grout testing were used in the Westinghouse Hanford Co. laboratory responsible for the grout performance testing. Detailed discussion of the lab. work and results are contained in this report
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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.
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Hazardous industrial waste management
International Nuclear Information System (INIS)
Quesada, Hilda; Salas, Juan Carlos; Romero, Luis Guillermo
2007-01-01
The appropriate managing of hazardous wastes is a problem little dealed in the wastes management in the country. A search of available information was made about the generation and handling to internal and external level of the hazardous wastes by national industries. It was worked with eleven companies of different types of industrial activities for, by means of a questionnaire, interviews and visits, to determine the degree of integral and suitable handling of the wastes that they generate. It was concluded that exist only some isolated reports on the generation of hazardous industrial wastes and handling. The total quantity of wastes generated in the country was impossible to establish. The companies consulted were deficient in all stages of the handling of their wastes: generation, accumulation and storage, transport, treatment and final disposition. The lack of knowledge of the legislation and of the appropriate managing of the wastes is showed as the principal cause of the poor management of the residues. The lack of state or private entities entrusted to give services of storage, transport, treatment and final disposition of hazardous wastes in the country was evident. (author) [es
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International Nuclear Information System (INIS)
Dupuis, M.C.
2007-01-01
Managing radioactive wastes used to be a peripheral activity for the French atomic energy commission (Cea). Over the past 40 years, it has become a full-fledged phase in the fuel cycle of producing electricity from the atom. In 2005, the national radioactive waste management agency (ANDRA) presented to the government a comprehensive overview of the results drawn from 15 years of research. This landmark report has received recognition beyond France's borders. By broadening this agency's powers, an act of 28 June 2006 acknowledges the progress made and the quality of the results. It also sets an objective for the coming years: work out solutions for managing all forms of radioactive wastes. The possibility of recovering wastes packages from the disposal site must be assured as it was asked by the government in 1998. The next step will be the official demand for the creation of a geological disposal site in 2016
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NWMO transportation technical work program
International Nuclear Information System (INIS)
Hatton, C.
2015-01-01
This paper describes technical work program for the transportation nuclear waste by the Nuclear Waste Management Organization (NWMO). Transportation work program involves risk assessment which under normal conditions involves dose assessment to the worker and the public as well as consideration of transportation system routing and operations. It also involves possible accident scenarios using forensic modelling and probability analysis.
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NWMO transportation technical work program
Energy Technology Data Exchange (ETDEWEB)
Hatton, C. [Nuclear Waste Management Organization, Toronto, ON (Canada)
2015-07-01
This paper describes technical work program for the transportation nuclear waste by the Nuclear Waste Management Organization (NWMO). Transportation work program involves risk assessment which under normal conditions involves dose assessment to the worker and the public as well as consideration of transportation system routing and operations. It also involves possible accident scenarios using forensic modelling and probability analysis.
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International Nuclear Information System (INIS)
Tirado-Soto, Magda Martina; Zamberlan, Fabio Luiz
2013-01-01
Highlights: ► In the marketing of recyclable materials, the waste-pickers are the least wins. ► It is proposed creating a network of recycling cooperatives to achieve viability. ► The waste-pickers contribute to waste management to the city. - Abstract: The objective of this study is to discuss the role of networks formed of waste-picker cooperatives in ameliorating problems of final disposal of solid waste in the city of Rio de Janeiro, since the city’s main landfill will soon have to close because of exhausted capacity. However, it is estimated that in the city of Rio de Janeiro there are around five thousand waste-pickers working in poor conditions, with lack of physical infrastructure and training, but contributing significantly by diverting solid waste from landfills. According to the Sustainable Development Indicators (IBGE, 2010a,b) in Brazil, recycling rates hover between 45% and 55%. In the municipality of Rio de Janeiro, only 1% of the waste produced is collected selectively by the government (COMLURB, 2010), demonstrating that recycling is mainly performed by waste-pickers. Furthermore, since the recycling market is an oligopsony that requires economies of scale to negotiate directly with industries, the idea of working in networks of cooperatives meets the demands for joint marketing of recyclable materials. Thus, this work presents a method for creating and structuring a network of recycling cooperatives, with prior training for working in networks, so that the expected synergies and joint efforts can lead to concrete results. We intend to demonstrate that it is first essential to strengthen the waste-pickers’ cooperatives in terms of infrastructure, governance and training so that solid waste management can be environmentally, socially and economically sustainable in the city of Rio de Janeiro
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Energy Technology Data Exchange (ETDEWEB)
Tirado-Soto, Magda Martina, E-mail: magda@pep.ufrj.br [Program of Production Engineering, School and Research in Engineering, Federal University of Rio de Janeiro (Brazil); Zamberlan, Fabio Luiz, E-mail: fabio@pep.ufrj.br [Program of Production Engineering, School and Research in Engineering, Federal University of Rio de Janeiro (Brazil)
2013-04-15
Highlights: ► In the marketing of recyclable materials, the waste-pickers are the least wins. ► It is proposed creating a network of recycling cooperatives to achieve viability. ► The waste-pickers contribute to waste management to the city. - Abstract: The objective of this study is to discuss the role of networks formed of waste-picker cooperatives in ameliorating problems of final disposal of solid waste in the city of Rio de Janeiro, since the city’s main landfill will soon have to close because of exhausted capacity. However, it is estimated that in the city of Rio de Janeiro there are around five thousand waste-pickers working in poor conditions, with lack of physical infrastructure and training, but contributing significantly by diverting solid waste from landfills. According to the Sustainable Development Indicators (IBGE, 2010a,b) in Brazil, recycling rates hover between 45% and 55%. In the municipality of Rio de Janeiro, only 1% of the waste produced is collected selectively by the government (COMLURB, 2010), demonstrating that recycling is mainly performed by waste-pickers. Furthermore, since the recycling market is an oligopsony that requires economies of scale to negotiate directly with industries, the idea of working in networks of cooperatives meets the demands for joint marketing of recyclable materials. Thus, this work presents a method for creating and structuring a network of recycling cooperatives, with prior training for working in networks, so that the expected synergies and joint efforts can lead to concrete results. We intend to demonstrate that it is first essential to strengthen the waste-pickers’ cooperatives in terms of infrastructure, governance and training so that solid waste management can be environmentally, socially and economically sustainable in the city of Rio de Janeiro.
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International Nuclear Information System (INIS)
1994-11-01
The objective of the Waste Area Grouping 1 Corehole 8 Removal Action is to collect strontium-90 contaminated groundwater that is currently being discharged from existing storm drains into First Creek. 90 Sr has been identified as a major contributor to potential risk offsite. First Creek contributes about 10% of the 90 Sr contamination detected at White Oak Dam. This Removal Action Work Plan (RAWP) addresses construction of new french drains, gravity piping, and a pressure sewer pipeline to collect and pump the contaminated water to Manhole 24. The contaminated water will then flow through existing pipes to the Process Waste Treatment Plant for treatment. The proposed scope of work for this project includes the installation of approximately 480 ft of high-density polyethylene gravity piping, with cleanouts, to transport the contaminated water to a proposed pumping station. The contaminated water will then be pumped from the new pump station approximately 1,140 ft through a new force main to Manhole 24. This project will reduce the quantity of 90 Sr contaminated groundwater entering First Creek
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CRISTOBAL GARCIA JORGE; VILA Marta; GIAVINI Michele; TORRES DE MATOS CRISTINA; MANFREDI SIMONE
2016-01-01
This report continues and further advances the work conducted by the JRC in the field of sustainable management of food waste, which resulted in the publication of the 2015 report “Improving Sustainability and Circularity of European Food Waste Management with a Life Cycle Approach”. It focuses on the broad European waste management context and, in particular, provides insight and analysis on the sustainability of food waste prevention strategies. Among other municipal waste streams, food ...
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An analysis of repository waste-handling operations
International Nuclear Information System (INIS)
Dennis, A.W.
1990-09-01
This report has been prepared to document the operational analysis of waste-handling facilities at a geologic repository for high-level nuclear waste. The site currently under investigation for the geologic repository is located at Yucca Mountain, Nye County, Nevada. The repository waste-handling operations have been identified and analyzed for the year 2011, a steady-state year during which the repository receives spent nuclear fuel containing the equivalent of 3000 metric tons of uranium (MTU) and defense high-level waste containing the equivalent of 400 MTU. As a result of this analysis, it has been determined that the waste-handling facilities are adequate to receive, prepare, store, and emplace the projected quantity of waste on an annual basis. In addition, several areas have been identified where additional work is required. The recommendations for future work have been divided into three categories: items that affect the total waste management system, operations within the repository boundary, and the methodology used to perform operational analyses for repository designs. 7 refs., 48 figs., 11 tabs
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Disposal of radioactive and other hazardous wastes
International Nuclear Information System (INIS)
Boge, R.; Bergman, C.; Bergvall, S.; Gyllander, C.
1989-01-01
The purpose of the workshop was discuss legal, scientific and practical aspects of disposal of low- and intermediate-level radioactive waste and other types of hazardous waste. During the workshop the non-radioactive wastes discussed were mainly wastes from energy production, but also industrial, chemical and household wastes. The workshop gave the participants the opportunity to exchange information on policies, national strategies and other important matters. A number of invited papers were presented and the participants brought background papers, describing the national situation, that were used in the working groups. One of the main aims of the workshop was to discuss if the same basic philosophy as that used in radiation protection could be used in the assessment of disposal of non-radioactive waste, as well as to come up with identifications of areas for future work and to propose fields for research and international cooperation. The main text of the report consists of a summary of the discussions and the conclusions reached by the workshop
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Energy Technology Data Exchange (ETDEWEB)
Suzuki, Y.; Maeda, A.; Sugikawa, S.; Takeshita, I. [Japan Atomic Energy Research Institute, Dept. of Safety Research Technical Support, Tokai-Mura, Naka-Gun, Ibaraki-Ken (Japan)
2000-07-01
In the NUCEF, the researches on criticality safety have been performed at two critical experiment facilities, STACY and TRACY in addition to the researches on fuel cycle such as advanced reprocessing and partitioning in alpha-gamma concrete cells and glove boxes. Many kinds of radioactive wastes have been generated through the research activities. Furthermore, the waste treatment itself may produce some secondary wastes. In addition, the separation and purification of plutonium of several tens-kg from MOX powder are scheduled in order to supply plutonium nitrate solution fuel for critical experiments at STACY. A large amount of wastes containing plutonium and americium will be generated from the plutonium fuel treatment. From the viewpoint of safety, the proper waste management is one of important works in NUCEF. Many efforts, therefore, have been made for the development of advanced waste treatment techniques to improve the waste management in NUCEF. Especially the reduction of alpha-contaminated wastes is a major interest. For example, the separation of americium is planned from the liquid waste evolved alter plutonium purification by application of tannin gel as an adsorbent of actinide elements. The waste management and the relating technological development in NUCEF are briefly described in this paper. (authors)
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International Nuclear Information System (INIS)
Suzuki, Y.; Maeda, A.; Sugikawa, S.; Takeshita, I.
2000-01-01
In the NUCEF, the researches on criticality safety have been performed at two critical experiment facilities, STACY and TRACY in addition to the researches on fuel cycle such as advanced reprocessing and partitioning in alpha-gamma concrete cells and glove boxes. Many kinds of radioactive wastes have been generated through the research activities. Furthermore, the waste treatment itself may produce some secondary wastes. In addition, the separation and purification of plutonium of several tens-kg from MOX powder are scheduled in order to supply plutonium nitrate solution fuel for critical experiments at STACY. A large amount of wastes containing plutonium and americium will be generated from the plutonium fuel treatment. From the viewpoint of safety, the proper waste management is one of important works in NUCEF. Many efforts, therefore, have been made for the development of advanced waste treatment techniques to improve the waste management in NUCEF. Especially the reduction of alpha-contaminated wastes is a major interest. For example, the separation of americium is planned from the liquid waste evolved alter plutonium purification by application of tannin gel as an adsorbent of actinide elements. The waste management and the relating technological development in NUCEF are briefly described in this paper. (authors)
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Management of Radioactive Wastes in Developing Countries
International Nuclear Information System (INIS)
Abdel Ghani, A.H.
1999-01-01
The management of radioactive wastes is one area of increasing interest especially in developing countries having more and more activities in the application of radioisotopes in medicine, research and industry. For a better understanding of radioactive waste management in developing countries this work will discuss the following items:Classification of countries with respect to waste management programs. Principal Radionuclides used in medicine, biological research and others and the range of radioactivity commonly used. Estimation of radioactive waste volumes and activities. Management of liquid wastes Collection. Treatment. Management of small volumes of organic liquid waste. Collection Treatment. Packaging and storage of radioactive wastes
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Tirado-Soto, Magda Martina; Zamberlan, Fabio Luiz
2013-04-01
The objective of this study is to discuss the role of networks formed of waste-picker cooperatives in ameliorating problems of final disposal of solid waste in the city of Rio de Janeiro, since the city's main landfill will soon have to close because of exhausted capacity. However, it is estimated that in the city of Rio de Janeiro there are around five thousand waste-pickers working in poor conditions, with lack of physical infrastructure and training, but contributing significantly by diverting solid waste from landfills. According to the Sustainable Development Indicators (IBGE, 2010a,b) in Brazil, recycling rates hover between 45% and 55%. In the municipality of Rio de Janeiro, only 1% of the waste produced is collected selectively by the government (COMLURB, 2010), demonstrating that recycling is mainly performed by waste-pickers. Furthermore, since the recycling market is an oligopsony that requires economies of scale to negotiate directly with industries, the idea of working in networks of cooperatives meets the demands for joint marketing of recyclable materials. Thus, this work presents a method for creating and structuring a network of recycling cooperatives, with prior training for working in networks, so that the expected synergies and joint efforts can lead to concrete results. We intend to demonstrate that it is first essential to strengthen the waste-pickers' cooperatives in terms of infrastructure, governance and training so that solid waste management can be environmentally, socially and economically sustainable in the city of Rio de Janeiro. Copyright © 2012 Elsevier Ltd. All rights reserved.
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Mixed waste characterization reference document
International Nuclear Information System (INIS)
1997-09-01
Waste characterization and monitoring are major activities in the management of waste from generation through storage and treatment to disposal. Adequate waste characterization is necessary to ensure safe storage, selection of appropriate and effective treatment, and adherence to disposal standards. For some wastes characterization objectives can be difficult and costly to achieve. The purpose of this document is to evaluate costs of characterizing one such waste type, mixed (hazardous and radioactive) waste. For the purpose of this document, waste characterization includes treatment system monitoring, where monitoring is a supplement or substitute for waste characterization. This document establishes a cost baseline for mixed waste characterization and treatment system monitoring requirements from which to evaluate alternatives. The cost baseline established as part of this work includes costs for a thermal treatment technology (i.e., a rotary kiln incinerator), a nonthermal treatment process (i.e., waste sorting, macronencapsulation, and catalytic wet oxidation), and no treatment (i.e., disposal of waste at the Waste Isolation Pilot Plant (WIPP)). The analysis of improvement over the baseline includes assessment of promising areas for technology development in front-end waste characterization, process equipment, off gas controls, and monitoring. Based on this assessment, an ideal characterization and monitoring configuration is described that minimizes costs and optimizes resources required for waste characterization
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Solidification of highly active wastes
International Nuclear Information System (INIS)
Morris, J.B.
1984-11-01
Final reports are presented on work on the following topics: glass technology; enhancement of off-gas aerosol collection; formation and trapping of volatile ruthenium; volatilisation of caesium, technetium and tellurium in high-level waste vitrification; deposition of ruthenium; and calcination of high-level waste liquors. (author)
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Waste management, waste resource facilities and waste conversion processes
International Nuclear Information System (INIS)
Demirbas, Ayhan
2011-01-01
In this study, waste management concept, waste management system, biomass and bio-waste resources, waste classification, and waste management methods have been reviewed. Waste management is the collection, transport, processing, recycling or disposal, and monitoring of waste materials. A typical waste management system comprises collection, transportation, pre-treatment, processing, and final abatement of residues. The waste management system consists of the whole set of activities related to handling, treating, disposing or recycling the waste materials. General classification of wastes is difficult. Some of the most common sources of wastes are as follows: domestic wastes, commercial wastes, ashes, animal wastes, biomedical wastes, construction wastes, industrial solid wastes, sewer, biodegradable wastes, non-biodegradable wastes, and hazardous wastes.
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Waste Management Information System (WMIS) User Guide
International Nuclear Information System (INIS)
Broz, R.E.
2008-01-01
This document provides the user of the Waste Management Information System (WMIS) instructions on how to use the WMIS software. WMIS allows users to initiate, track, and close waste packages. The modular design supports integration and utilization of data through the various stages of waste management. The phases of the waste management work process include generation, designation, packaging, container management, procurement, storage, treatment, transportation, and disposal
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Waste Management Information System (WMIS) User Guide
Energy Technology Data Exchange (ETDEWEB)
R. E. Broz
2008-12-22
This document provides the user of the Waste Management Information System (WMIS) instructions on how to use the WMIS software. WMIS allows users to initiate, track, and close waste packages. The modular design supports integration and utilization of data throuh the various stages of waste management. The phases of the waste management work process include generation, designation, packaging, container management, procurement, storage, treatment, transportation, and disposal.
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Secondary Waste Form Down-Selection Data Package—Fluidized Bed Steam Reforming Waste Form
Energy Technology Data Exchange (ETDEWEB)
Qafoku, Nikolla; Westsik, Joseph H.; Strachan, Denis M.; Valenta, Michelle M.; Pires, Richard P.
2011-09-12
The Hanford Site in southeast Washington State has 56 million gallons of radioactive and chemically hazardous wastes stored in 177 underground tanks (ORP 2010). The U.S. Department of Energy (DOE), Office of River Protection (ORP), through its contractors, is constructing the Hanford Tank Waste Treatment and Immobilization Plant (WTP) to convert the radioactive and hazardous wastes into stable glass waste forms for disposal. Within the WTP, the pretreatment facility will receive the retrieved waste from the tank farms and separate it into two treated process streams. These waste streams will be vitrified, and the resulting waste canisters will be sent to offsite (high-level waste [HLW]) and onsite (immobilized low-activity waste [ILAW]) repositories. As part of the pretreatment and ILAW processing, liquid secondary wastes will be generated that will be transferred to the Effluent Treatment Facility (ETF) on the Hanford Site for further treatment. These liquid secondary wastes will be converted to stable solid waste forms that will be disposed of in the Integrated Disposal Facility (IDF). To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions (WRPS) has initiated secondary waste form testing work at Pacific Northwest National Laboratory (PNNL). In anticipation of a down-selection process for a waste form for the Solidification Treatment Unit to be added to the ETF, PNNL is developing data packages to support that down-selection. The objective of the data packages is to identify, evaluate, and summarize the existing information on the four waste forms being considered for stabilizing and solidifying the liquid secondary wastes. At the Hanford Site, the FBSR process is being evaluated as a supplemental technology for treating and immobilizing Hanford LAW radioactive tank waste and for treating secondary wastes from the WTP pretreatment and LAW vitrification processes.
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Evaluation of bitumens for nuclear facilities radioactive waste immobilization
International Nuclear Information System (INIS)
Guzella, Marcia F.R.; Silva, Tania V. da; Loiola, Roberto; Monte, Lauro J.B.
2000-01-01
The activities developed at the Nuclear Technology Development Centre, Centro de Desenvolvimento da Tecnologia Nuclear - CDTN/CNEN, include the research and development work of the radioactive wastes immobilization in different kind of bitumen. The present work describes the bituminization of simulated low level wastes of evaporator concentrates.Two types of bitumen are used for incorporation of the simulated wastes generated by nuclear power plants. Studies on rheological properties, leaching data, differential thermoanalysis and water content of the waste-products have been carried out. (author)
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Depleted uranium munitions - where are we now?
International Nuclear Information System (INIS)
Spratt, Brian G.
2002-01-01
There are very different views on the health hazards of DU munitions. Most of the concerns of veterans and their advisors focus on the radiological effects of DU and consequently these are the focus of this editorial. Effects on the kidney and environmental consequences are, however, considered in the second of the Royal Society reports and the main conclusions of both of the reports are outlined in the summary document published in this issue of the journal. The main radiological concerns focus on the irradiation of lung tissues from inhaled DU particles and irradiation resulting from the translocation of inhaled particles to the thoracic lymph nodes.The overwhelming scientific view, presented in the two Royal Society reports and in other independent reviews, is that the main risks of exposure to DU aerosols are an increase in lung cancer and (from chemical toxicity) damage to the kidney, although these are likely to be evident only following substantial intakes. The equivalent doses to the thoracic lymph nodes following inhalation of DU particles are about ten times greater than those to the lung, but the former tissue is considered to be relatively insensitive to radiation-induced cancers. So far, large-scale epidemiological studies of UK and US Gulf War veterans have shown no increase in mortality from cancer, or kidney disease, but these studies need to be continued to see if any significant excess mortality from these causes appears. As mentioned previously, more sensitive epidemiological studies should be possible if groups of soldiers who have known exposures to DU can be identified. Adverse reproductive effects have been observed in rodents exposed to uranium although most of these effects are evident after relatively large daily intakes of uranium. The possibility of effects on reproductive health (from DU or other toxic exposures) is being studied in both UK and US Gulf War veterans. Results from the UK epidemiological study are not yet available but
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Status of Pantex Plant Waste Management Project/program control system
International Nuclear Information System (INIS)
Price, Wesley J.; Matthews, William L.
1992-01-01
During a December 1990 Waste Management Program Review held in Albuquerque, New Mexico, the Waste Management and Operational Surety Division (WMOSD) introduced the project control system to be used for the Waste Management (WM) Operations Program. The system was entitled 'TRAC-WM' (Tracking and Control for Waste Management). The stated objective for this system was to establish a frame work for planning, managing, and controlling work within the WM program. As a result Mason and Hanger (the operating contractor at the Pantex Plant) initiated the development of a computerized waste management project tracking system. (author)
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Hanford site waste tank characterization
International Nuclear Information System (INIS)
De Lorenzo, D.S.; Simpson, B.C.
1994-08-01
This paper describes the on-going work in the characterization of the Hanford-Site high-level waste tanks. The waste in these tanks was produced as part of the nuclear weapons materials processing mission that occupied the Hanford Site for the first 40 years of its existence. Detailed and defensible characterization of the tank wastes is required to guide retrieval, pretreatment, and disposal technology development, to address waste stability and reactivity concerns, and to satisfy the compliance criteria for the various regulatory agencies overseeing activities at the Hanford Site. The resulting Tank Characterization Reports fulfill these needs, as well as satisfy the tank waste characterization milestones in the Hanford Federal Facility Agreement and Consent Order
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Long-term high-level waste technology. Composite quarterly technical report, July-September 1980
International Nuclear Information System (INIS)
Cornman, W.R.
1981-02-01
This composite quarterly technical report summarizes work performed at participating sites to immobilize high-level radioactive wastes. The technical information included in this report is structured along the lines of the Work Breakdown Structure adopted for use in the High-Level Waste Management Technology (WBS) program. The functions and work elements of the WBS are as follows: function 1 - program management and support, which includes work elements of management and budget, environmental and safety assessments, and other support; function 2 - waste preparation, which includes in-situ storage or disposal, waste retrieval, and separation and concentration; function 3 - waste fixation with work elements of waste form development and characterization, and process and equipment development; and function 4 - final handling which includes canister development and characterization, and onsite storage or disposal
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Future strategic directions for radioactive waste management programmes
International Nuclear Information System (INIS)
Anon.
1999-01-01
The NEA Radioactive Waste Management Committee (RWMC) has identified six strategic areas as priorities for work in the coming years. These strategic areas, listed in this paper, are described in a NEA publication (Strategic Areas in Waste Management: the viewpoint and work orientations of the NEA RWMC
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International Nuclear Information System (INIS)
Albrecht, E.; Kuehn, K.
1977-01-01
Final storage of nuclear wastes in the salt mine at Asse is described. Until the end of 1976, all in all 73,000 containers with slightly radioactive wastes were deposited there within the framework of a test programme - the Asse pit is a pilot plant. Final storage of medium active waste was started in 1972. So far, about 1,150 barrels with medium active waste were deposited. Storage techniques applied, radiation exposure of the personnel and experience gained so far are reported on in this context. Final storage at Asse of highly active wastes developing decay heat is still in a preparatory stage, as here radiation as well as heat problems have to be mastered. Technical mining activities for the recoverable storage of highly-active, heat-developing wastes in the form of ceramic glasses are still in a planning phase, whereas advance work, e.g. cutting storage chambers out of seams 775 m thick have already begun. (HPH) [de
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Waste Feed Evaporation Physical Properties Modeling
International Nuclear Information System (INIS)
Daniel, W.E.
2003-01-01
This document describes the waste feed evaporator modeling work done in the Waste Feed Evaporation and Physical Properties Modeling test specification and in support of the Hanford River Protection Project (RPP) Waste Treatment Plant (WTP) project. A private database (ZEOLITE) was developed and used in this work in order to include the behavior of aluminosilicates such a NAS-gel in the OLI/ESP simulations, in addition to the development of the mathematical models. Mathematical models were developed that describe certain physical properties in the Hanford RPP-WTP waste feed evaporator process (FEP). In particular, models were developed for the feed stream to the first ultra-filtration step characterizing its heat capacity, thermal conductivity, and viscosity, as well as the density of the evaporator contents. The scope of the task was expanded to include the volume reduction factor across the waste feed evaporator (total evaporator feed volume/evaporator bottoms volume). All the physical properties were modeled as functions of the waste feed composition, temperature, and the high level waste recycle volumetric flow rate relative to that of the waste feed. The goal for the mathematical models was to predict the physical property to predicted simulation value. The simulation model approximating the FEP process used to develop the correlations was relatively complex, and not possible to duplicate within the scope of the bench scale evaporation experiments. Therefore, simulants were made of 13 design points (a subset of the points used in the model fits) using the compositions of the ultra-filtration feed streams as predicted by the simulation model. The chemistry and physical properties of the supernate (the modeled stream) as predicted by the simulation were compared with the analytical results of experimental simulant work as a method of validating the simulation software
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Melter development needs assessment for RWMC buried wastes
International Nuclear Information System (INIS)
Donaldson, A.D.; Carpenedo, R.J.; Anderson, G.L.
1992-02-01
This report presents a survey and initial assessment of the existing state-of-the-art melter technology necessary to thermally treat (stabilize) buried TRU waste, by producing a highly leach resistant glass/ceramic waste form suitable for final disposal. Buried mixed transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) represents an environmental hazard requiring remediation. The Environmental Protection Agency (EPA) placed the INEL on the National Priorities List in 1989. Remediation of the buried TRU-contaminated waste via the CERCLA decision process is required to remove INEL from the National Priorities List. A Waste Technology Development (WTD) Preliminary Systems Design and Thermal Technologies Screening Study identified joule-heated and plasma-heated melters as the most probable thermal systems technologies capable of melting the INEL soil and waste to produce the desired final waste form [Iron-Enriched Basalt (IEB) glass/ceramic]. The work reported herein then surveys the state of existing melter technology and assesses it within the context of processing INEL buried TRU wastes and contaminated soils. Necessary technology development work is recommended
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Technical area status report for low-level mixed waste final waste forms
International Nuclear Information System (INIS)
Mayberry, J.L.; Huebner, T.L.; Ross, W.; Nakaoka, R.; Schumacher, R.; Cunnane, J.; Singh, D.; Darnell, R.; Greenhalgh, W.
1993-08-01
This report presents information on low-level mixed waste forms.The descriptions of the low-level mixed waste (LLMW) streams that are considered by the Mixed Waste Integrated Program (MWIP) are given in Appendix A. This information was taken from descriptions generated by the Mixed Waste Treatment Program (MWTP). Appendix B provides a list of characteristic properties initially considered by the Final Waste Form (FWF) Working Group (WG). A description of facilities available to test the various FWFs discussed in Volume I of DOE/MWIP-3 are given in Appendix C. Appendix D provides a summary of numerous articles that were reviewed on testing of FWFS. Information that was collected by the tests on the characteristic properties considered in this report are documented in Appendix D. The articles reviewed are not a comprehensive list, but are provided to give an indication of the data that are available
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Waste-to-energy: Dehalogenation of plastic-containing wastes.
Shen, Yafei; Zhao, Rong; Wang, Junfeng; Chen, Xingming; Ge, Xinlei; Chen, Mindong
2016-03-01
The dehalogenation measurements could be carried out with the decomposition of plastic wastes simultaneously or successively. This paper reviewed the progresses in dehalogenation followed by thermochemical conversion of plastic-containing wastes for clean energy production. The pre-treatment method of MCT or HTT can eliminate the halogen in plastic wastes. The additives such as alkali-based metal oxides (e.g., CaO, NaOH), iron powders and minerals (e.g., quartz) can work as reaction mediums and accelerators with the objective of enhancing the mechanochemical reaction. The dehalogenation of waste plastics could be achieved by co-grinding with sustainable additives such as bio-wastes (e.g., rice husk), recyclable minerals (e.g., red mud) via MCT for solid fuels production. Interestingly, the solid fuel properties (e.g., particle size) could be significantly improved by HTT in addition with lignocellulosic biomass. Furthermore, the halogenated compounds in downstream thermal process could be eliminated by using catalysts and adsorbents. Most dehalogenation of plastic wastes primarily focuses on the transformation of organic halogen into inorganic halogen in terms of halogen hydrides or salts. The integrated process of MCT or HTT with the catalytic thermal decomposition is a promising way for clean energy production. The low-cost additives (e.g., red mud) used in the pre-treatment by MCT or HTT lead to a considerable synergistic effects including catalytic effect contributing to the follow-up thermal decomposition. Copyright © 2015 Elsevier Ltd. All rights reserved.
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International Nuclear Information System (INIS)
Perz, K.
2001-06-01
The Austrian Waste Management Act (AWG) entered into force on 1 July 1990. Paragraph 1 of the act defines the following objectives: to keep detrimental, unbeneficial or otherwise unhealthy influences on man, as well as on animals, plants, their living conditions and their natural environment as low as possible; to preserve raw material and energy resources; to keep the demand for landfill capacities as low as possible; to ensure that only such materials should remain as waste, the dumping of which does not present any potential hazard for future generations (precautionary principle). The waste management act thus places the highest priority on the protection of human beings and the environment and upon the preservation of natural resources. Accordingly, it must be the aim of waste management to handle waste in such a way that environmental pollution is kept as low as possible by prevention, recovery and disposal. Paragraph 5 of the Austrian waste management act stipulates that the Federal Minister of Agriculture, Forestry, Environment and Water Management has to issue the Federal Waste Management Plan in order to reach the objectives and observing the rules of modern waste management. Following the first waste management plan in 1992 an amendment is required every three years. This is why the Austrian Federal Environment Agency elaborated the following studies: waste generation, recovery and disposal in Austria; hazardous waste and waste oils in Austria; non-hazardous waste in Austria. Further information on waste management facilities in Austria is presented on our homepage (http://www.ubavie.gv.at). (author)
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Research programme on radioactive wastes - Synthesis report 2009
International Nuclear Information System (INIS)
Brander, S.
2010-02-01
This short synthesis report for the Swiss Federal Office of Energy (SFOE) issued by the head of the programme on radioactive wastes reports on activities during the year 2009. Background information on the definition of topics to be focussed on is briefly presented. In particular, topics such as communication with the general public, knowledge-saving and marking concepts for radioactive wastes are noted. Work done in these areas as well as on waste management in general are discussed. Conferences held and the transfer of know-how are noted, as is cooperation with foreign organisations active in the area of nuclear research and waste management. Finally, work planned for 2010 is noted
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The DWPF waste form qualification program
International Nuclear Information System (INIS)
Marra, S.L.; Plodinec, M.J.
1994-01-01
Prior to the introduction of radioactive feed into the Defense Waste Processing Facility for immobilization in borosilicate glass an extensive waste qualification program must be completed. The DWPF must demonstrate its ability to comply with the Waste Acceptance Product Specifications. This ability is being demonstrated through laboratory and pilot scale work and will be completed after the full operation of the DWPF using various simulated feeds
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Quality of Life at Work: A study conducted in an organization of waste collection not dangerous
Directory of Open Access Journals (Sweden)
Grasiele Cabral Pereira
2018-04-01
Full Text Available Incluir o resumo em inglês. This article aims to elaborate a diagnosis of a not dangerous waste collection organization, that seeks to analyze which factors determine the quality of life of the employees of the organization. Nadler and Lawler (1983 affirm that Quality of Life at Work is a way of thinking about individuals, work and the company itself. This research is characterized as exploratory, descriptive and quantitative with the use of statistics and application of a questionnaire aiming to identify the Quality of Life at Work of this specific company. The questionnaire applied was created through the interpretation and analysis of the eight dimensions of QWL presented by Walton (1973. As for the population, an intentional sample was used, comprising the employees of the administrative sector. As for the analysis carried out from the graphs, it was verified that the organization provides a good quality of life to its employees, since just a small percentages of respondents did not agree in part or did not agree with some of the affirmative questions obtained.
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Methods for maintaining a record of waste packages during waste processing and storage
International Nuclear Information System (INIS)
2005-01-01
During processing, radioactive waste is converted into waste packages, and then sent for storage and ultimately for disposal. A principal condition for acceptance of a waste package is its full compliance with waste acceptance criteria for disposal or storage. These criteria define the radiological, mechanical, physical, chemical and biological properties of radioactive waste that can, in principle, be changed during waste processing. To declare compliance of a waste package with waste acceptance criteria, a system for generating and maintaining records should be established to record and track all relevant information, from raw waste characteristics, through changes related to waste processing, to final checking and verification of waste package parameters. In parallel, records on processing technology and the operational parameters of technological facilities should adhere to established and approved quality assurance systems. A records system for waste management should be in place, defining the data to be collected and stored at each step of waste processing and using a reliable selection process carried over into the individual steps of the waste processing flow stream. The waste management records system must at the same time ensure selection and maintenance of all the main information, not only providing evidence of compliance of waste package parameters with waste acceptance criteria but also serving as an information source in the case of any future operations involving the stored or disposed waste. Records generated during waste processing are a constituent part of the more complex system of waste management record keeping, covering the entire life cycle of radioactive waste from generation to disposal and even the post-closure period of a disposal facility. The IAEA is systematically working on the preparation of a set of publications to assist its Member States in the development and implementation of such a system. This report covers all the principal
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Biogas-centred domestic waste recycling system
Energy Technology Data Exchange (ETDEWEB)
Gupta, C L
1983-04-01
In fast developing suburban towns, there is an urgent need for an integrated system for waste recycling and energy and fertiliser supply on a single house basis. This is because even though toilet waste is handled by a septic tank-soak pit arrangement, kitchen and bathroom water and solid organic wastes have to be discharged outside the house. A biogas based domestic waste recycling system has been designed and constructed and has been successfully working. Some salient features of this plant are discussed here.
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Embedding of reactor wastes in plastic resins
International Nuclear Information System (INIS)
1979-01-01
STEAG Kernenergie GmbH is so far the only firm commercially to condition radioactive bead ion exchange resins by embedding in polystyrene resins. The objective of the work reported here was to study and develop methods for immobilization of other reactor wastes in plastic resins. Comparison studies on high quality cement however showed favourable results for cement with respect to process safety and economy. For this reason STEAG interrupted its work in the field of resin embedding after about one year. The work carried out during this period is surveyed in this report, which includes a comprehensive literature study on reactor wastes and their solidification in plastic resins as well as on regulations with regard to radioactive waste disposal in the member states of the European Communities
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Technology development activities supporting tank waste remediation
International Nuclear Information System (INIS)
Bonner, W.F.; Beeman, G.H.
1994-06-01
This document summarizes work being conducted under the U.S. Department of Energy's Office of Technology Development (EM-50) in support of the Tank Waste Remediation System (TWRS) Program. The specific work activities are organized by the following categories: safety, characterization, retrieval, barriers, pretreatment, low-level waste, and high-level waste. In most cases, the activities presented here were identified as supporting tank remediation by EM-50 integrated program or integrated demonstration lead staff and the selections were further refined by contractor staff. Data sheets were prepared from DOE-HQ guidance to the field issued in September 1993. Activities were included if a significant portion of the work described provides technology potentially needed by TWRS; consequently, not all parts of each description necessarily support tank remediation
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International Nuclear Information System (INIS)
1994-01-01
This report is the summary of the reports on radiation control and others submitted by those who installed practical power reactor facilities based on the relevant law in fiscal 1993. The amounts of release of radioactive gaseous and liquid wastes were sufficiently smaller than the target value of the yearly release control for attaining the target value of dose that the public around the facilities receive. As to the state of control of radioactive solid waste, the amount of drum generation tended to decrease year by year, and the cumulative amount to be preserved tended to level off. The dose equivalent that the individuals who engaged in radiation works received was smaller than the limit value in all nuclear power stations. The total dose equivalent for those workers in fiscal 1993 was 86.65 man Sv. Hereafter, the automation and remote operation of works, the water quality control for reducing crud and so on will be promoted to reduce radiation exposure. The reference data on the state of control of gaseous, liquid and solid wastes, and the state of control of radiation exposure of workers are attached. (K.I.)
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Waste assaying and radiation monitoring equipment at the waste management centre of NPP Leningrad
Directory of Open Access Journals (Sweden)
Šokčić-Kostić Marina
2006-01-01
Full Text Available The waste accumulated in the past at the Nuclear Power Plant Leningrad has to be sorted and packed in an optimal way. In the area of waste treatment and management, the completeness and quality of direct monitoring are of the outmost importance for the validity of, and confidence in, both practicable waste management options and calculations of radiological impacts. Special monitoring systems are needed for this purpose. Consistent with the scale of work during the waste treatment procedures and the complexity of the plant data have to be collected from characteristic parts in various treatment stages. To combine all the information, a tracking procedure is needed during the waste treatment process to characterize the waste for interim and/or final disposal. RWE NUKEM GmbH has developed special customer-tailored systems which fulfill the specifications required by plant operation and by the authorities.
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A comparative assessment of alternative waste management procedures for selected reprocessing wastes
International Nuclear Information System (INIS)
Hickford, G.E.; Plews, M.J.
1983-07-01
This report, which has been prepared by Associated Nuclear Services for the Department of the Environment, presents the results of a study and comparative assessment of management procedures for low and intermediate level solid waste streams arising from current and future fuel reprocessing operations on the Sellafield site. The characteristics and origins of the wastes under study are discussed and a reference waste inventory is presented, based on published information. Waste management strategy in the UK and its implications for waste conditioning, packaging and disposal are discussed. Wastes currently arising which are not suitable for Drigg burial or sea dumping are stored in an untreated form. Work is in hand to provide additional and improved disposal facilities which will accommodate all the waste streams under study. For each waste stream viable procedures are identified for further assessment. The procedures comprise a series of on-site operations-recovery from storage, pre-treatment, treatment, encapsulation, and packaging, prior to storage or disposal of the conditioned waste form. Assessments and comparisons of each procedure for each waste are presented. These address various process, operational, economic, radiological and general safety factors. The results are presented in a series of tables with supporting text. For the majority of wastes direct encapsulation with minimal treatment appears to be a viable procedure. Occupational exposure and general safety are not identified as significant factors governing the choice of procedures. The conditioned wastes meet the general requirements for safe handling during storage and transportation. The less active wastes suitable for disposal by currently available routes meet the appropriate disposal criteria. It is not possible to consider in detail the suitability for disposal of the more active wastes for which disposal facilities are not yet available. (Author)
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(Pleurotus pulmonarius) grown on cotton waste and cassava peel
African Journals Online (AJOL)
This work evaluated the yield of Pleurotus pulmonarius on different mixtures of cotton waste and cassava peel. P. pulmonarius demonstrated significantly higher colonization rate on cotton waste substrate (100 g cotton waste) 3 weeks after inoculation of spawn than any other substrate mixtures. Cotton waste had the ...
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Waste transmutation and public acceptance
International Nuclear Information System (INIS)
Pigford, T.H.
1991-01-01
The concept of transmuting radioactive wastes with reactors or accelerators is appealing. It has the potential of simplifying or eliminating problems of disposing of nuclear waste. The transmutation concept has been renewed vigorously at a time when national projects to dispose of high-level and transuranic waste are seriously delayed. In this period of tightening federal funds and program curtailments, skilled technical staffs are available at US Department of Energy (DOE) national laboratories and contractors to work on waste transmutation. If the claims of transmutation can be shown to be realistic, economically feasible, and capable of being implemented within the US institutional infrastructure, public acceptance of nuclear waste disposal may be enhanced. If the claims for transmutation are not substantiated, however, there will result a serious loss of credibility and an unjust exacerbation of public concerns about nuclear waste. The paper discusses the following topics: how public acceptance is achieved; the technical community and waste disposal; transmutation and technical communication; transmutation issues; technical fixes and public perception
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Status of mixed-waste regulation
International Nuclear Information System (INIS)
Bahadur, S.
1988-01-01
Mixed waste is waste containing radionuclides regulated by the US Nuclear Regulatory Commission (NRC) under the Atomic Energy Act, as well as hazardous waste materials regulated by the Environmental Protection Agency (EPA) under the Resource Conservation and Recovery Act (RCRA). This has led to a situation of dual regulation in which both NRC and EPA regulate the same waste under requirements that at times appear conflicting. The NRC has been working with the EPA to resolve the issues associated with the dual regulation of mixed waste. Discussions between the two agencies indicate that dual regulation of mixed wastes appears technically achievable, although the procedures may be complex and burdensome to the regulated community. The staffs of both agencies have been coordinating their efforts to minimize the burden of dual regulation on state agencies and the industry. Three major issues were identified as sources of potential regulatory conflict: (a) definition and identification of mixed waste, (b) siting guidelines for disposal facilities, and (c) design concepts for disposal units
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Cadmium-containing waste and recycling possibilities
International Nuclear Information System (INIS)
Wiegand, V.; Rauhut, A.
1981-01-01
To begin with, the processes of cadmium production from zinc ores in smelting plants or from intermediates of other metal works are described. A considerable amount of the cadmium is obtained in the recycling process in zinc, lead, and copper works. The way of the cadmium-containing intermediaries, processing, enrichment, and disposal of cadmium waste are described. Uses of cadmium and its compounds are mentioned, and cadmium consumption in the years 1973-1977 in West Germany is presented in a table. Further chapters discuss the production and the way of waste during production and processing of cadmium-containing products, the problem of cadmium in household refuse and waste incineration plants, and the problem of cadmium emissions. (IHOE) [de
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Waste analysis plan for T Plant Complex
International Nuclear Information System (INIS)
Williams, J.F.
1996-01-01
Washington Administration Code 173-303-300 requires that a waste analysis plan (WAP) be provided by a treatment, storage, and/or disposal (TSD) unit to confirm their knowledge about a dangerous and/or mixed waste to ensure that the waste is managed properly. The specific objectives of the WAP are as follows: Ensure safe management of waste during treatment and storage; Ensure that waste generated during operational activities is properly designated in accordance with regulatory requirements; Provide chemical and physical analysis of representative samples of the waste stored for characterization and/or verification before the waste is transferred to another TSD unit; Ensure compliance with land disposal restriction (LDR) requirements for treated waste; and Provide basis for work plans that describes waste analysis for development of new treatment technologies
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Waste minimization applications at a remediation site
International Nuclear Information System (INIS)
Allmon, L.A.
1995-01-01
The Fernald Environmental Management Project (FEMP) owned by the Department of Energy was used for the processing of uranium. In 1989 Fernald suspended production of uranium metals and was placed on the National Priorities List (NPL). The site's mission has changed from one of production to environmental restoration. Many groups necessary for producing a product were deemed irrelevant for remediation work, including Waste Minimization. Waste Minimization does not readily appear to be applicable to remediation work. Environmental remediation is designed to correct adverse impacts to the environment from past operations and generates significant amounts of waste requiring management. The premise of pollution prevention is to avoid waste generation, thus remediation is in direct conflict with this premise. Although greater amounts of waste will be generated during environmental remediation, treatment capacities are not always available and disposal is becoming more difficult and costly. This creates the need for pollution prevention and waste minimization. Applying waste minimization principles at a remediation site is an enormous challenge. If the remediation site is also radiologically contaminated it is even a bigger challenge. Innovative techniques and ideas must be utilized to achieve reductions in the amount of waste that must be managed or dispositioned. At Fernald the waste minimization paradigm was shifted from focusing efforts on source reduction to focusing efforts on recycle/reuse by inverting the EPA waste management hierarchy. A fundamental difference at remediation sites is that source reduction has limited applicability to legacy wastes but can be applied successfully on secondary waste generation. The bulk of measurable waste reduction will be achieved by the recycle/reuse of primary wastes and by segregation and decontamination of secondary wastestreams. Each effort must be measured in terms of being economically and ecologically beneficial
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International Nuclear Information System (INIS)
Kuznick, S.K.
1985-01-01
Two pieces of legislation have been enacted in the United States to provide a framework for the management of radioactive waste and spent nuclear fuel: the Low-level Radioactive Waste Policy Act (1980) and the Nuclear Waste Policy Act of 1982. Neither of these statutes provide a means for resolving third party liability issues arising out of radioactive waste management. However, the Price Anderson Act (originally enacted in 1957) provides a system of financial protection that can be applied to waste management activities and that can resolve most issues pertaining to liability for nuclear damage that may result from long-term management of radioactive waste and spent nuclear fuel. (NEA) [fr
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International Nuclear Information System (INIS)
Burbank, D.A. Jr.; Weingardt, K.M.
1993-10-01
A testing program has been conducted by the Westinghouse Hanford Company to confirm the baseline waste form selection for use in Waste Receiving and Processing (WRAP) Module 2A. WRAP Module 2A will provide treatment required to properly dispose of containerized contact-handled, mixed low-level waste at the US Department of Energy Hanford Site in south-central Washington State. Solidification/stabilization has been chosen as the appropriate treatment for this waste. This work is intended to test cement-based, thermosetting polymer, and thermoplastic polymer solidification media to substantiate the technology approach for WRAP Module 2A. Screening tests were performed using the major chemical constituent of each waste type to measure the gross compatibility with the immobilization media and to determine formulations for more detailed testing. Surrogate materials representing each of the eight waste types were prepared in the laboratory. These surrogates were then solidified with the selected immobilization media and subjected to a battery of standard performance tests. Detailed discussion of the laboratory work and results are contained in this report
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Waste disposal developments within BNFL
International Nuclear Information System (INIS)
Johnson, L.F.
1989-01-01
British Nuclear Fuels plc has broad involvement in topics of radioactive waste generation, treatment, storage and disposal. The Company's site at Drigg has been used since 1959 for the disposal of low level waste and its facilities are now being upgraded and extended for that purpose. Since September 1987, BNFL on behalf of UK Nirex Limited has been managing an investigation of the Sellafield area to assess its suitability for deep underground emplacement of low and intermediate level radioactive wastes. An approach will be described to establish a partnership with the local community to work towards a concept of monitored, underground emplacement appropriate for each waste category. (author)
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Sensor Technology Assessment for Ordnance and Explosive Waste Detection and Location. Revision B.
1995-03-01
249 A ppendices ................................................................................................ 255 Appendix A...military purposes. Dogs. noted for their acute sense of smell, provide a quick and effective method for OEW detection. Explosive munitions in or out of...odor, which the dog detects through its acute sense of smell. They are also trained to detect and respond to visual clues such as metal or plastic
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Technological and organizational aspects of radioactive waste management
International Nuclear Information System (INIS)
2005-01-01
This document comprises collected lecture on radioactive waste management which were given by specialists of the Radioactive Waste Management Section of the IAEA, scientific-industrial enterprise 'Radon' (Moscow, RF) and A.A. Bochvar's GNTs RF VNIINM (Moscow, RF) on various courses, seminars and conferences. These lectures include the following topics: basic principles and national systems of radioactive waste management; radioactive waste sources and their classification; collection, sorting and initial characterization of radioactive wastes; choice of technologies of radioactive waste processing and minimization of wastes; processing and immobilization of organic radioactive wastes; thermal technologies of radioactive waste processing; immobilization of radioactive wastes in cements, asphalts, glass and polymers; management of worked out closed radioactive sources; storage of radioactive wastes; deactivation methods; quality control and assurance in radioactive waste management
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International Nuclear Information System (INIS)
1992-05-01
On behalf of the Federal Minister of Research and Technology, the Kernforschungszentrum Karlsruhe has undertaken the projekt management of the R and D programme sector of waste management, subdivided into the programmes decommissioning and nuclear fuel cycle, and ultimate disposal of dangerous wastes. Ultimate disposal of dangerous wastes is understood to be the ultimate disposal of radioactive wastes and the dumping of chemical-toxic wastes. The progress report documents its programme sector of waste management. Its main part contains the formalized interim reports (as of 31.12.1991) on all projects attended by the manager of the waste management project, arranged according to promotion marks (letter C in the promotion mark stands for chemical-toxic, E for ultimate disposal, S for decommisioning, W for reprocessing, and U - for historical reasons - for university project). (orig./BBR) [de
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Transportation of radioactive wastes from nuclear fuel cycles
International Nuclear Information System (INIS)
1979-09-01
This paper discusses current and foreseen radioactive waste transportation systems as they apply to the INFCE Working Group 7 study. The types of wastes considered include spent fuel, which is treated as a waste in once-through fuel cycles; high-, medium-, and low-level waste; and gaseous waste. Regulatory classification of waste quantities and containers applicable to these classifications are discussed. Radioactive wastes are presently being transported in a safe and satisfactory manner. None of the INFCE candidate fuel cycles pose any extraordinary problems to future radioactive waste transportation and such transportation will not constitute a decisive factor in the choice of a preferred fuel cycle
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International Nuclear Information System (INIS)
Marsh, J.D.; McCarthy, J.F.
1994-07-01
This Work Plan/Site Safety and Health Plan (SSHP) and the attached work plan are for the performance of the colloid sampling project at WAG 5. The work will be conducted by the Oak Ridge National Laboratory (ORNL) Environmental Sciences Division (ESD) and associated ORNL environmental, safety, and health support groups. This activity will fall under the scope of 29 CFR 1910.120, Hazardous Waste Operations and Emergency Response (HAZWOPER). The purpose of this document is to establish health and safety guidelines to be followed by all personnel involved in conducting work for this project. Work will be conducted in accordance with requirements as stipulated in the ORNL HAZWOPER Program manual, and applicable ORNL, Martin Marietta Energy Systems, Inc., and US Department of Energy (DOE) policies and procedures
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Stabilization of compactible waste
International Nuclear Information System (INIS)
Franz, E.M.; Heiser, J.H. III; Colombo, P.
1990-09-01
This report summarizes the results of series of experiments performed to determine the feasibility of stabilizing compacted or compactible waste with polymers. The need for this work arose from problems encountered at disposal sites attributed to the instability of this waste in disposal. These studies are part of an experimental program conducted at Brookhaven National Laboratory (BNL) investigating methods for the improved solidification/stabilization of DOE low-level wastes. The approach taken in this study was to perform a series of survey type experiments using various polymerization systems to find the most economical and practical method for further in-depth studies. Compactible dry bulk waste was stabilized with two different monomer systems: styrene-trimethylolpropane trimethacrylate (TMPTMA) and polyester-styrene, in laboratory-scale experiments. Stabilization was accomplished by wetting or soaking compactible waste (before or after compaction) with monomers, which were subsequently polymerized. Three stabilization methods are described. One involves the in-situ treatment of compacted waste with monomers in which a vacuum technique is used to introduce the binder into the waste. The second method involves the alternate placement and compaction of waste and binder into a disposal container. In the third method, the waste is treated before compaction by wetting the waste with the binder using a spraying technique. A series of samples stabilized at various binder-to-waste ratios were evaluated through water immersion and compression testing. Full-scale studies were conducted by stabilizing two 55-gallon drums of real compacted waste. The results of this preliminary study indicate that the integrity of compacted waste forms can be readily improved to ensure their long-term durability in disposal environments. 9 refs., 10 figs., 2 tabs
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International Nuclear Information System (INIS)
Ishiguro, Hideharu; Hayashi, Masaru; Senda, Masaki
2008-01-01
Radioactive Waste Management and Nuclear Facility Decommissioning Technology Center (RANDEC) has investigated the feasibility study on the business of collection and storage of many kinds of low level radioactive waste in radioactive facilities. This works include the total volume of waste, conceptual design of storage facility and cost estimation of construction and operation of this business. This paper describes the some points of the results of this study. (author)
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Eighteenth annual report of: The Radioactive Waste Management Advisory Committee
International Nuclear Information System (INIS)
1998-07-01
This annual report reviews the RWMAC's work programme and progress made in 1997-1998; discusses operational and administrative matters including financial management and policy review; and presents the 1998 RWMAC work programme. Particular chapters are devoted to the management of intermediate and high level radioactive waste and spent fuel; the Dounreay Nuclear Establishment; the radioactive waste discharge authorisations. The document presents the RWMAC's review of the Ministry of Defence's radioactive waste management practices. A separate chapter is devoted to the study of radioactive waste management practices in Spain. Annexes to the report include terms of reference and membership of the Radioactive Waste Management Advisory Committee; RWMAC financial statement; declaration and register of member's interests; the RWMAC's 1998 work programme; the RWMAC's response to the Government on Proposals for the control and remediation of radioactively contaminated land
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Arc plasma incineration of surrogate radioactive wastes
International Nuclear Information System (INIS)
Girold, C.; Cartier, R.; Taupiac, J.P.; Vandensteendam, C.; Baronnet, J.M.
1995-01-01
The aim of this presentation is to demonstrate the feasibility to substitute a single plasma reactor, where the arc is transferred on a melt glass bath, for several steps in an existing nuclear technological wastes incinerator. The incineration of wastes, the produced gas treatment and the vitrification of ashes issued from waste incineration are the three simultaneous functions of this new kind of reactor. The three steps of the work are described: first, post-combustion in an oxygen plasma of gases generated from the waste pyrolysis, then, vitrification of ashes from the calcination of wastes in the transferred plasma furnace and finally, incineration/vitrification of wastes in the same furnace
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International Nuclear Information System (INIS)
Balcazar, M.; Flores R, J.H.; Pena, P.; Lopez, A.
2006-01-01
The acceptance of the Nuclear Energy as electric power supply implies to give answer to the population on the two main challenges to conquer in the public opinion: the nuclear accidents and the radioactive wastes. Several of the questions that are made on the radioactive wastes, its are the mobility migration of them, the geologic stability of the place where its are deposited and the possible migration toward the aquifer mantels. Since the half lives of the radioactive waste of a Nuclear Reactor are of several hundred of thousands of years, the technical explanations to the previous questions little convince to the public in general. In this work summary the results of the radioactive waste generated in a natural reactor, denominated Oklo effect that took place in Gabon, Africa, it makes several thousands of millions of years, a lot before the man appeared in the Earth. The identification of at least 17 reactors in Oklo it was carried out thanks to the difference in the concentrations of Uranium 235 and 238 prospective, and to the analysis of the non-mobility of the radioactive waste in the site. It was able by this way to determine that the reactors with sizes of hardly some decimeter and powers of around 100 kilowatts were operating in intermittent and spontaneous form for space of 150,000 years, with operation cycles of around 30 minutes. Recent studies have contributed information valuable on the natural confinement of the radioactive waste of the Oklo reactors in matrixes of minerals of aluminum phosphate that caught and immobilized them for thousands of millions of years. This extracted information from the nature contributes guides and it allows 'to verify' the validity of the current proposals on the immobilization of radioactive wastes of a nuclear reactor. This work presents in clear and accessible form to the public in general on the secure 'design', operation, 'decommissioning' and 'storage' of the radioactive waste of the reactors that the nature put
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PD and I works to improve the waste solidification performance of Angra 1
International Nuclear Information System (INIS)
Tello, Cledola C.O. de; Gomes, Nelson J.P.O.
2009-01-01
Angra 1 Power Plant is the first Brazilian NPP, and started its commercial operation in 1985. The wastes from its operation are spent ion exchange resins, expended filter cartridges, boric acid evaporator concentrates; and solid wastes such as gloves, cleaning tools, plastics and protective clothing. Liquid waste streams are treated by evaporation to reduce the volume, and the concentrate is solidified in cement. The original cementation unit was designed to meet the US product acceptance criteria of the early seventies, when environmental and safety requirements were less restrictive than now. This system had a very low efficiency, and the waste product quality was very poor. A new solidification plant was bought, and R and D project was carried out to study and develop a suitable cementation process and the PCP - process control program - to guarantee the licensing of the plant and maximize its efficiency using Brazilian materials. To accomplish these objectives, a huge amount of experiments were carried on. Tests were performed to determine the main properties of the process and the product, e.g. the workability, set time, compressive strength (stress resistance) and leachability. After reaching the established parameters, the mixture system was optimized. The paddle and container designs were modified and also the motor specifications, so that the process efficiency could be improved. The performance of this new system is increased allowing solidifying from 56 till 69% in volume of waste, much better in comparison of the old one, whose maximum value was about 20%. (author)
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Waste Management System Requirements Document
International Nuclear Information System (INIS)
1992-02-01
This DCP establishes an interim plan for the Office of Civilian Radioactive Waste Management (OCRWM) technical baseline until the results of the OCRWM Document Hierarchy Task Force can be implemented. This plan is needed to maintain continuity in the Program for ongoing work in the areas of Waste Acceptance, Transportation, Monitored Retrievable Storage (MRS) and Yucca Mountain Site Characterization
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Two-stage agglomeration of fine-grained herbal nettle waste
Obidziński, Sławomir; Joka, Magdalena; Fijoł, Olga
2017-10-01
This paper compares the densification work necessary for the pressure agglomeration of fine-grained dusty nettle waste, with the densification work involved in two-stage agglomeration of the same material. In the first stage, the material was pre-densified through coating with a binder material in the form of a 5% potato starch solution, and then subjected to pressure agglomeration. A number of tests were conducted to determine the effect of the moisture content in the nettle waste (15, 18 and 21%), as well as the process temperature (50, 70, 90°C) on the values of densification work and the density of the obtained pellets. For pre-densified pellets from a mixture of nettle waste and a starch solution, the conducted tests determined the effect of pellet particle size (1, 2, and 3 mm) and the process temperature (50, 70, 90°C) on the same values. On the basis of the tests, we concluded that the introduction of a binder material and the use of two-stage agglomeration in nettle waste densification resulted in increased densification work (as compared to the densification of nettle waste alone) and increased pellet density.
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NWTS waste package program plan. Volume I. Program strategy, description, and schedule
International Nuclear Information System (INIS)
1981-10-01
This document describes the work planned for developing the technology to design, test and produce packages used for the long-term isolation of nuclear waste in deep geologic repositories. Waste forms considered include spent fuel and high-level waste. The testing and selection effort for barrier materials for radionuclide containment is described. The NWTS waste package program is a design-driven effort; waste package conceptual designs are used as input for preliminary designs, which are upgraded to a final design as materials and testing data become available. Performance assessment models are developed and validated. Milestones and a detailed schedule are given for the waste package development effort. Program logic networks defining work flow, interfaces among the NWTS Projects, and interrelationships of specific activities are presented. Detailed work elements are provided for the Waste Package Program Plan subtasks - design and development, waste form, barrier materials, and performance evaluation - for salt and basalt, host rocks for which the state of waste package knowledge and the corresponding data base are advanced
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International Nuclear Information System (INIS)
1985-01-01
This book deals mainly with decommissioning problems concerning more particularly dismantling and decontamination techniques, and radioactive waste processing. Radioactive waste management in France and the French regulation are tackled. Equipments developed for works in hostile environment are also presented [fr
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The long-term management of radioactive waste
International Nuclear Information System (INIS)
Faussat, A.
1988-01-01
After setting out the terms of reference of ANDRA (National agency for the management of radioactive waste), the author describes the current situation and the projects for the surface storage of waste of low and medium activity. He then discusses the work which has started on the construction of an underground laboratory for studying the storage of long life waste [fr
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40 CFR 256.05 - Annual work program.
2010-07-01
... FOR DEVELOPMENT AND IMPLEMENTATION OF STATE SOLID WASTE MANAGEMENT PLANS Purpose, General Requirements... included by reference in the annual work program: (1) Substate solid waste management plans, (2) Plans for the development of facilities and services, including hazardous waste management facilities and...
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The Waste Negotiator's mission
International Nuclear Information System (INIS)
Bataille, Christian
1993-01-01
The mission of the Waste Negotiator is to seek out sites for deep underground laboratories to study their potential for disposal of high level radioactive waste. Although appointed by the government, he acts independently. In 1990, faced by severe public criticism at the way that the waste disposal was being handled, and under increasing pressure to find an acceptable solution, the government stopped the work being carried out by ANDRA (Agence nationale pour la gestion des dechets radioactifs) and initiated a full review of the issues involved. At the same time, parliament also started its own extensive investigation to find a way forward. These efforts finally led to the provision of a detailed framework for the management of long lived radioactive waste, including the construction of two laboratories to investigate possible repository sites. The Waste Negotiator was appointed to carry out a full consultative process in the communities which are considering accepting an underground laboratory. (Author)
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Waste pipe calculus extensions
International Nuclear Information System (INIS)
O'Connell, W.J.
1979-01-01
The waste pipe calculus provides a rapid method, using Laplace transforms, to calculate the transport of a pollutant such as nuclear waste, by a network of one-dimensional flow paths. The present note extends previous work as follows: (1) It provides an alternate approximation to the time-domain function (inverse Laplace transform) for the resulting transport. This algebraic approximation may be viewed as a simpler and more approximate model of the transport process. (2) It identifies two scalar quantities which may be used as summary consequence measures of the waste transport (or inversely, waste retention) system, and provides algebraic expressions for them. (3) It includes the effects of radioactive decay on the scalar quantity results, and further provides simplifying approximations for the cases of medium and long half-lives. This algebraic method can be used for quick approximate analyses of expected results, uncertainty and sensitivity, in evaluating selection and design choices for nuclear waste disposal systems
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The 2016-2018 French National Plan for Radioactive Materials and Waste Management
International Nuclear Information System (INIS)
Kassiotis, Christophe
2016-01-01
The main conclusions of the 2016-2018 PNGMDR: Waste requiring specific work - → Continue the search for an appropriate disposal route for tritiated waste, in particular from the small producers; → Monitor the deployment of used sealed source management routes; → Continue work to take charge of waste with no disposal route, more specifically mercury and organic waste and activated parts from small producers; → Search for and implement a final management solution for the waste stored in the ECRIN BNI
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Radiological assessment of the radioactive wastes management
International Nuclear Information System (INIS)
Domenech Nieves, Haydee; Hernandez Saiz, Alejandro
1996-01-01
In the work are obtained the dose values resulting from the evaluation of the conditioning operations of wastes in the scenarios of exposure that are mentioned and are compared with the dose restriction suggested for the moment for such tasks. The radioactive wastes that are evaluated in the work are: liquids -both those from the generating institutions and the ones stored in the Managua- located deposit, Radon-226 not-in-use solids and sources 226: the results demonstrate that it is possible to treat in a year the total volume of the liquid and solid radioactive wastes as well as a large number of sources of Radon-226
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Comparative assessment of alternative cycles for waste heat recovery and upgrade
International Nuclear Information System (INIS)
Little, Adrienne B.; Garimella, Srinivas
2011-01-01
Thermally activated systems based on sorption cycles, as well as mechanical systems based on vapor compression/expansion are assessed in this study for waste heat recovery applications. In particular, ammonia-water sorption cycles for cooling and mechanical work recovery, a heat transformer using lithium bromide-water as the working fluid pair to yield high temperature heat, and organic Rankine cycles using refrigerant R245fa for work recovery as well as versions directly coupled to a vapor compression cycle to yield cooling are analyzed with overall heat transfer conductances for heat exchangers that use similar approach temperature differences for each cycle. Two representative cases are considered, one for smaller-scale and lower temperature applications using waste heat at 60 o C, and the other for larger-scale and higher temperature waste heat at 120 o C. Comparative assessments of these cycles on the basis of efficiencies and system footprints guide the selection of waste heat recovery and upgrade systems for different applications and waste heat availabilities. Furthermore, these considerations are used to investigate four case studies for waste heat recovery for data centers, vehicles, and process plants, illustrating the utility and limitations of such solutions. The increased implementation of such waste heat recovery systems in a variety of applications will lead to decreased primary source inputs and sustainable energy utilization. -- Highlights: → Sorption and mechanical pathways for the conversion of waste heat streams to work, cooling, and temperature boosting were investigated. → Waste heat sources including 300 W of energy at 60 o C and 1 kW of energy at 120 o C were analyzed. → Up to about seventy percent of the input waste heat can be converted to cooling. → Up to about ten percent can be converted to work. → Up to about 47 percent can be upgraded to a higher temperature.
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Large packages for reactor decommissioning waste
International Nuclear Information System (INIS)
Price, M.S.T.
1991-01-01
This study was carried out jointly by the Atomic Energy Establishment at Winfrith (now called the Winfrith Technology Centre), Windscale Laboratory and Ove Arup and Partners. The work involved the investigation of the design of large transport containers for intermediate level reactor decommissioning waste, ie waste which requires shielding, and is aimed at European requirements (ie for both LWR and gas cooled reactors). It proposes a design methodology for such containers covering the whole lifetime of a waste disposal package. The design methodology presented takes account of various relevant constraints. Both large self shielded and returnable shielded concepts were developed. The work was generic, rather than specific; the results obtained, and the lessons learned, remain to be applied in practice
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Radioactive waste management - an educational challenge
International Nuclear Information System (INIS)
Tulenko, J.S.
1991-01-01
University Radioactive Waste Management educational programs are being actively advanced by the educational support activities of the Offices of Civilian Radioactive Waste Management (OCRWM) and Environmental Restoration and Waste Management (ERWM) of the DOE. The DOE fellowship program formats of funding students and requiring a practical research experience (practicum) at a DOE site has helped to combine the academic process with a practical work experience. Support for faculty in these programs is augmenting the benefits of the fellowship programs. The many job opportunities and funding sources for students which currently exists in the radioactive waste management area are fueling an increase in academic programs seeking recognition of their radioactive waste management curriculums
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Quality control in the radioactive waste management
International Nuclear Information System (INIS)
Rzyski, B.M.
1989-01-01
Radioactive waste management as in industrial activities must mantain in all steps a quality control programme. This control extended from materials acquisition, for waste treatment, to the package deposition is one of the most important activities because it aims to observe the waste acceptance criteria in repositories and allows to guarantee the security of the nuclear facilities. In this work basic knowledges about quality control in waste management and some examples of adopted procedures in other countries are given. (author) [pt
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2007 Global Demilitarization Symposium and Exhibition
2007-05-17
Directorate Design Development - Cryofracture Subsystem - • Munitions Preparation Trailer – Munition loading fixtures to ensure proper orientation – Conveyor ...in cryobath – Empty fixture return heater – Conveyor to transfer munitions to Cryofracture Press Trailer • Cryofracture Press Trailer – 3.0 lbs. (TNT...diverters to separate fracture munitions into four feed chutes – Press munitions loader robot to transfer munitions to press Energetics, Warheads
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Energy Technology Data Exchange (ETDEWEB)
Jantzen, C. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Pierce, E. M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bannochie, C. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Burket, P. R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Cozzi, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Crawford, C. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Daniel, W. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Fox, K. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Herman, C. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Miller, D. H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Missimer, D. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nash, C. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Williams, M. F. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Brown, C. F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Qafoku, N. P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Neeway, J. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Valenta, M. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gill, G. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Swanberg, D. J. [Washington River Protection Solutions (WRPS), Richland, WA (United States); Robbins, R. A. [Washington River Protection Solutions (WRPS), Richland, WA (United States); Thompson, L. E. [Washington River Protection Solutions (WRPS), Richland, WA (United States)
2015-10-01
This report describes the benchscale testing with simulant and radioactive Hanford Tank Blends, mineral product characterization and testing, and monolith testing and characterization. These projects were funded by DOE EM-31 Technology Development & Deployment (TDD) Program Technical Task Plan WP-5.2.1-2010-001 and are entitled “Fluidized Bed Steam Reformer Low-Level Waste Form Qualification”, Inter-Entity Work Order (IEWO) M0SRV00054 with Washington River Protection Solutions (WRPS) entitled “Fluidized Bed Steam Reforming Treatability Studies Using Savannah River Site (SRS) Low Activity Waste and Hanford Low Activity Waste Tank Samples”, and IEWO M0SRV00080, “Fluidized Bed Steam Reforming Waste Form Qualification Testing Using SRS Low Activity Waste and Hanford Low Activity Waste Tank Samples”. This was a multi-organizational program that included Savannah River National Laboratory (SRNL), THOR® Treatment Technologies (TTT), Pacific Northwest National Laboratory (PNNL), Oak Ridge National Laboratory (ORNL), Office of River Protection (ORP), and Washington River Protection Solutions (WRPS). The SRNL testing of the non-radioactive pilot-scale Fluidized Bed Steam Reformer (FBSR) products made by TTT, subsequent SRNL monolith formulation and testing and studies of these products, and SRNL Waste Treatment Plant Secondary Waste (WTP-SW) radioactive campaign were funded by DOE Advanced Remediation Technologies (ART) Phase 2 Project in connection with a Work-For-Others (WFO) between SRNL and TTT.
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Sustainable treatment of municipal waste water
DEFF Research Database (Denmark)
Hansen, Peter Augusto; Larsen, Henrik Fred
The main goal of the EU FP6 NEPTUNE program is to develop new and improve existing waste water treatment technologies (WWTT) and sludge handling technologies for municipal waste water, in accordance with the concepts behind the EU Water Framework Directive. As part of this work, the project.......e. heavy metals, pharmaceuticals and endocrine disruptors) in the waste water. As a novel approach, the potential ecotoxicity and human toxicity impacts from a high number of micropollutants and the potential impacts from pathogens will be included. In total, more that 20 different waste water and sludge...... treatment technologies are to be assessed. This paper will present the first LCA results from running existing life cycle impact assessment (LCIA) methodology on some of the waste water treatment technologies. Keywords: Sustainability, LCA, micropollutants, waste water treatment technologies....
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Final disposal of radioactive wastes
Energy Technology Data Exchange (ETDEWEB)
Kroebel, R [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Wiederaufarbeitung und Abfallbehandlung; Krause, H [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Abt. zur Behandlung Radioaktiver Abfaelle
1978-08-01
This paper discusses the final disposal possibilities for radioactive wastes in the Federal Republic of Germany and the related questions of waste conditioning, storage methods and safety. The programs in progress in neighbouring CEC countries and in the USA are also mentioned briefly. The autors conclude that the existing final disposal possibilities are sufficiently well known and safe, but that they could be improved still further by future development work. The residual hazard potential of radioactive wastes from fuel reprocessing after about 1000 years of storage is lower that of known inorganic core deposits.
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Kotwicki, Lech; Grzelak, Katarzyna; Bełdowski, Jacek
2016-06-01
Assessment of biological effects of chemical warfare agents (CWAs) dumped in the Baltic Sea has been one of the tasks of the Chemical Munitions Search & Assessment (CHEMSEA) project. Three sites have been selected for investigation: Bornholm Deep, Gotland Deep and Gdansk Deep. Fauna collected from these locations were compared with the reference area located between the studied regions at similar depths below 70 m. In total, four scientific cruises occurred in different seasons between 2011 and 2013. The total lack of any representatives of macrozoobenthos in all of the investigated dumping sites was noted. As a practical matter, the Baltic deeps were inhabited by nematodes as the only meiofauna representatives. Therefore, nematodes were used as a key group to explore the faunal communities inhabiting chemical dumping sites in the Baltic deeps. In total, 42 nematode genera belonging to 18 families were identified, and the dominant genus was Sabatieria (Comesomatidae), which constituted 37.6% of the overall nematode community. There were significant differences in nematode community structure (abundance and taxa composition) between the dumping areas and the reference site (Kruskal-Wallis H=30.96, pnematode assemblages could mirror the environmental conditions.
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Radioactive alpha wastes processing at the nuclear center of Mol
International Nuclear Information System (INIS)
Voorde, N. van de
1978-01-01
This process is based on calcination at very high temperature (1500 0 C) of wastes, mainly burnable, with selected non-burnable wastes, such as glass, metal, sludge, ion echanger, etc. Incineration wastes melt at this temperature and an insoluble granitic mass is obtained. This operation is performed in a special oven equipped with a gas purification device installed in a place like alpha bearing wastes treatment working spot where the staff can work in an air-supplied suit. Two incineration units are planned, the first one with a capacity of 150 kg/hr in view to treat a large amount of wastes with a low plutonium content (max. 10 mg/l), the second smaller with a capacity of 10 kg/hr, specially designed to process wastes with a high Pu content. This project for the first unit, at least is now tested with beta gamma wastes processing. Alpha bearing wastes pocessing will start at the end of 1978, we are now building the second unit [fr
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Food waste and the food-energy-water nexus: A review of food waste management alternatives.
Kibler, Kelly M; Reinhart, Debra; Hawkins, Christopher; Motlagh, Amir Mohaghegh; Wright, James
2018-04-01
Throughout the world, much food produced is wasted. The resource impact of producing wasted food is substantial; however, little is known about the energy and water consumed in managing food waste after it has been disposed. Herein, we characterize food waste within the Food-Energy-Water (FEW) nexus and parse the differential FEW effects of producing uneaten food and managing food loss and waste. We find that various food waste management options, such as waste prevention, landfilling, composting, anaerobic digestion, and incineration, present variable pathways for FEW impacts and opportunities. Furthermore, comprehensive sustainable management of food waste will involve varied mechanisms and actors at multiple levels of governance and at the level of individual consumers. To address the complex food waste problem, we therefore propose a "food-waste-systems" approach to optimize resources within the FEW nexus. Such a framework may be applied to devise strategies that, for instance, minimize the amount of edible food that is wasted, foster efficient use of energy and water in the food production process, and simultaneously reduce pollution externalities and create opportunities from recycled energy and nutrients. Characterization of FEW nexus impacts of wasted food, including descriptions of dynamic feedback behaviors, presents a significant research gap and a priority for future work. Large-scale decision making requires more complete understanding of food waste and its management within the FEW nexus, particularly regarding post-disposal impacts related to water. Copyright © 2018 Elsevier Ltd. All rights reserved.
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Savannah River waste management program plan
International Nuclear Information System (INIS)
1980-04-01
This document provides the program plan as requested by the Savannah River Operations Office of the Department of Energy. The plan was developed to provide a working knowledge of the nature and extent of the waste management programs being undertaken by Savannah River contractors for the Fiscal Year 1980. In addition, the document projects activities for several years beyond 1980 to adequately plan for safe handling and storage of radioactive wastes generated at Savannah River, for developing technology to immobilize high-level radioactive wastes generated and stored at SR, and for developing technology for improved management of low-level solid wastes
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ICRP guidance on radioactive waste disposal
International Nuclear Information System (INIS)
Cooper, J.R.
2002-01-01
The International Commission on Radiological Protection (ICRP) issued recommendations for a system of radiological protection in 1991 as the 1990 Recommendations. Guidance on the application of these recommendations in the general area of waste disposal was issued in 1997 as Publication 77 and guidance specific to disposal of solid long-lived radioactive waste was issued as Publication 81. This paper summarises ICRP guidance in radiological protection requirements for waste disposal concentrating on the ones of relevance to the geological disposal of solid radioactive waste. Suggestions are made for areas where further work is required to apply the ICRP guidance. (author)
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Strategy and technologies of 'Shelter' radioactive waste management
International Nuclear Information System (INIS)
Aleshin, A.M.; Batij, V.G.; Klyuchnikov, A.A.; Korchagin, P.A.; Rud'ko, V.M.; Saverskij, S.Yu.; Stoyanov, A.I.; Shcherbin, V.N.; Shcherbina, V.G.
1997-01-01
The main directions of technical activity under the Chernobyl NPP 'Shelter' waste management during its transformation to ecologically safe system are determined. Comprehensive classification of 'Shelter' radioactive waste according to the requirements of the Ukrainian laws and normative documents was worked out for the first time. The sequence of works was proposed in accordance with the decisions of the Ukrainian government and with works on 'Shelter' condition stabilization and preparation for Chernobyl NPP decommissioning. 1 figs
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The limitation of radioactive wastes from hospitals
International Nuclear Information System (INIS)
Schuurman, B.; IJtsma, D.; Zwigt, A.
1987-01-01
Interviews were made with radiation experts working at hospitals about the treatment and limiting of radioactive wastes. The authors conclude that with the aid of hospital personnel a decrease of the volume of radioactive waste is possible. 25 refs
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Transuranic waste: long-term planning
International Nuclear Information System (INIS)
Young, K.C.
1985-07-01
Societal concerns for the safe handling and disposal of toxic waste are behind many of the regulations and the control measures in effect today. Transuranic waste, a specific category of toxic (radioactive) waste, serves as a good example of how regulations and controls impact changes in waste processing - and vice versa. As problems would arise with waste processing, changes would be instituted. These changes improved techniques for handling and disposal of transuranic waste, reduced the risk of breached containment, and were usually linked with regulatory changes. Today, however, we face a greater public awareness of and concern for toxic waste control; thus, we must anticipate potential problems and work on resolving them before they can become real problems. System safety analyses are valuable aids in long-term planning for operations involving transuranic as well as other toxic materials. Examples of specific system safety analytical methods demonstrate how problems can be anticipated and resolution initiated in a timely manner having minimal impacts upon allocation of resource and operational goals. 7 refs., 1 fig
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Estimate of Hanford Waste Rheology and Settling Behavior
International Nuclear Information System (INIS)
Poloski, Adam P.; Wells, Beric E.; Tingey, Joel M.; Mahoney, Lenna A.; Hall, Mark N.; Thomson, Scott L.; Smith, Gary Lynn; Johnson, Michael E.; Meacham, Joseph E.; Knight, Mark A.; Thien, Michael G.; Davis, Jim J.; Onishi, Yasuo
2007-01-01
The U.S. Department of Energy (DOE) Office of River Protection's Waste Treatment and Immobilization Plant (WTP) will process and treat radioactive waste that is stored in tanks at the Hanford Site. Piping, pumps, and mixing vessels have been selected to transport, store, and mix the high-level waste slurries in the WTP. This report addresses the analyses performed by the Rheology Working Group (RWG) and Risk Assessment Working Group composed of Pacific Northwest National Laboratory PNNL, Bechtel National Inc. (BNI), CH2M HILL, DOE Office of River Protection (ORP) and Yasuo Onishi Consulting, LLC staff on data obtained from documented Hanford waste analyses to determine a best-estimate of the rheology of the Hanford tank wastes and their settling behavior. The actual testing activities were performed and reported separately in referenced documentation. Because of this, many of the required topics below do not apply and are so noted
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Vitrification: a solution for the wastes of wastes; La vitrification: ca chauffe pour les ultimes
Energy Technology Data Exchange (ETDEWEB)
Guihard, B. [Europlasma, 33 - Saint Medard en Jalles (France)
1997-07-01
The incineration of wastes generates other wastes (fly ashes) that concentrate a large amount of polluting substances (heavy metals, salts..). French law requires a stabilization of this kind of wastes before their storage. Today vitrification can be considered as an alternative to the stabilization and storage way, the vitrified products could be seen as an interesting material in the building industry or in road works. A few years ago the municipality of Bordeaux decided to launch a demonstration program and a REFIOM (fly ashes) vitrification unit has been operating since 1997. (A.C.)
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2006-01-01
We should like to remind you that you can have all commonplace, conventional waste (combustible, inert, wood, etc.) disposed of by the TS-FM Group. Requests for the removal of such waste should be made by contacting FM Support on tel. 77777 or by e-mail (Fm.Support@cern.ch). For requests to be acted upon, the following information must be communicated to FM Support: budget code to be debited for the provision and removal of the skip / container. type of skip required (1m3, 4 m3, 7 m3, 15 m3, 20 m3, 30 m3). nature of the waste to be disposed of (bulky objects, cardboard boxes, etc.). building concerned. details of requestor (name, phone number, department, group, etc.). We should also like to inform you that the TS-FM Group can arrange for waste to be removed from work-sites for firms under contract to CERN, provided that the prior authorisation of the CERN Staff Member in charge of the contract is obtained and the relevant disposal/handling charges are paid. You are reminded that the selective sorting o...
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2006-01-01
We should like to remind you that you can have all commonplace, conventional waste (combustible, inert, wood, etc.) disposed of by the TS-FM Group. Requests for the removal of such waste should be made by contacting FM Support on tel. 77777 or by e-mail (Fm.Support@cern.ch). For requests to be acted upon, the following information must be communicated to FM Support: budget code to be debited for the provision and removal of the skip / container; type of skip required (1m3, 4 m3, 7 m3, 15 m3, 20 m3, 30 m3); nature of the waste to be disposed of (bulky objects, cardboard boxes, etc.); building concerned; details of requestor (name, phone number, department, group, etc.). We should also like to inform you that the TS-FM Group can arrange for waste to be removed from work-sites for firms under contract to CERN, provided that the prior authorisation of the CERN Staff Member in charge of the contract is obtained and the relevant disposal/handling charges are paid. You are reminded that the selective sorting...
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The waste originating from nuclear energy peaceful applications and its management
International Nuclear Information System (INIS)
Souza, Jair Albo Marques de
1997-05-01
This work presents the waste originating from nuclear energy and its management. It approaches the following main topics: nature and classification of the wastes; security requirements to the waste management; state of the art related to the wastes derivates of the uses of the nuclear energy; wastes in the fuel cycle; wastes of the industrial, medical and research and development applications; costs of the waste management
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Effect of color removal agent on textiles waste water
International Nuclear Information System (INIS)
Khomsaton Abu Bakar; Selambakknu, Sarala; Jamaliah Shariff; Ting, Teo Ming; Khairul Zaman Dahlan
2010-01-01
The effect of color removal agent (CRA) on textile waste water has been studied. The aim of this work is to determine the optimum condition for CRA to react on the textile waste water and to see the effect of CRA on waste water with different Chemical Oxygen Demand. 8 ml CRA was used to treat 800 mls of sample with various COD ranging between 2500 mg/ l-500 mg/ l. The results showed that CRA totally remove the colour of textile waste water at pH ranging from 6 to 8. At an optimum condition CRA works efficiently on waste water with COD 2300 mg/ l for reduction of suspended solid and turbidity. It also observed, sludge accumulation was depended on COD concentration. Color removal curves for different initial COD concentration also obtained. (author)
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High Level Radioactive Waste Management
International Nuclear Information System (INIS)
1991-01-01
The proceedings of the second annual international conference on High Level Radioactive Waste Management, held on April 28--May 3, 1991, Las Vegas, Nevada, provides information on the current technical issue related to international high level radioactive waste management activities and how they relate to society as a whole. Besides discussing such technical topics as the best form of the waste, the integrity of storage containers, design and construction of a repository, the broader social aspects of these issues are explored in papers on such subjects as conformance to regulations, transportation safety, and public education. By providing this wider perspective of high level radioactive waste management, it becomes apparent that the various disciplines involved in this field are interrelated and that they should work to integrate their waste management activities. Individual records are processed separately for the data bases
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DISPOSABLE CANISTER WASTE ACCEPTANCE CRITERIA
Energy Technology Data Exchange (ETDEWEB)
R.J. Garrett
2001-07-30
The purpose of this calculation is to provide the bases for defining the preclosure limits on radioactive material releases from radioactive waste forms to be received in disposable canisters at the Monitored Geologic Repository (MGR) at Yucca Mountain. Specifically, this calculation will provide the basis for criteria to be included in a forthcoming revision of the Waste Acceptance System Requirements Document (WASRD) that limits releases in terms of non-isotope-specific canister release dose-equivalent source terms. These criteria will be developed for the Department of Energy spent nuclear fuel (DSNF) standard canister, the Multicanister Overpack (MCO), the naval spent fuel canister, the High-Level Waste (HLW) canister, the plutonium can-in-canister, and the large Multipurpose Canister (MPC). The shippers of such canisters will be required to demonstrate that they meet these criteria before the canisters are accepted at the MGR. The Quality Assurance program is applicable to this calculation. The work reported in this document is part of the analysis of DSNF and is performed using procedure AP-3.124, Calculations. The work done for this analysis was evaluated according to procedure QAP-2-0, Control of Activities, which has been superseded by AP-2.21Q, Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities. This evaluation determined that such activities are subject to the requirements of DOE/RW/0333P, Quality Assurance Requirements and Description (DOE 2000). This work is also prepared in accordance with the development plan titled Design Basis Event Analyses on DOE SNF and Plutonium Can-In-Canister Waste Forms (CRWMS M&O 1999a) and Technical Work Plan For: Department of Energy Spent Nuclear Fuel Work Packages (CRWMS M&O 2000d). This calculation contains no electronic data applicable to any electronic data management system.
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International Nuclear Information System (INIS)
Chung, Chul-Woo; Turo, Laura A.; Ryan, Joseph V.; Johnson, Bradley R.; McCloy, John S.
2013-01-01
Highlights: ► Cast Stone: Portland cement, fly ash, blast furnace slag, and simulated nuclear waste. ► Caustic secondary waste from the off-gas of a vitrification process was targeted. ► Crystallinity, micro- and mesostructure, and engineering properties characterized. ► Waste concentration varied from 0 to 2.5 M, but caused minimal changes. ► Cast Stone shows good compositional versatility as a secondary waste form. -- Abstract: Cement-based waste forms have long been considered economical technologies for disposal of various types of waste. A solidified cementitious waste form, Cast Stone, has been identified to immobilize the radioactive secondary waste from vitrification processes. In this work, Cast Stone was considered for a Na-based caustic liquid waste, and its physical properties were analyzed as a function of liquid waste loading up to 2 M Na. Differences in crystallinity (phase composition), microstructure, mesostructure (pore size distribution and surface area), and macrostructure (density and compressive strength) were investigated using various analytical techniques, in order to assess the suitability of Cast Stone as a chemically durable waste. It was found that the concentration of secondary waste simulant (caustic waste) had little effect on the relevant engineering properties of Cast Stone, showing that Cast Stone could be an effective and tolerant waste form for a wide range of concentrations of high sodium waste
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Energy Technology Data Exchange (ETDEWEB)
González Pericot, N., E-mail: natalia.gpericot@upm.es [Escuela Técnica Superior de Edificación, Universidad Politécnica de Madrid, Calle Juan de Herrera n°6, 28040 Madrid (Spain); Villoria Sáez, P., E-mail: paola.villoria@upm.es [Escuela Técnica Superior de Edificación, Universidad Politécnica de Madrid, Calle Juan de Herrera n°6, 28040 Madrid (Spain); Del Río Merino, M., E-mail: mercedes.delrio@upm.es [Escuela Técnica Superior de Edificación, Universidad Politécnica de Madrid, Calle Juan de Herrera n°6, 28040 Madrid (Spain); Liébana Carrasco, O., E-mail: oscar.liebana@uem.es [Escuela de Arquitectura, Universidad Europea de Madrid, Calle Tajo s/n, 28670 Villaviciosa de Odón (Spain)
2014-11-15
Highlights: • On-site segregation level: 1.80%; training and motivation strategies were not effective. • 70% Cardboard waste: from switches and sockets during the building services stage. • 40% Plastic waste: generated during structures and partition works due to palletizing. • >50% Wood packaging waste, basically pallets, generated during the envelope works. - Abstract: The construction sector is responsible for around 28% of the total waste volume generated in Europe, which exceeds the amount of household waste. This has led to an increase of different research studies focusing on construction waste quantification. However, within the research studies made, packaging waste has been analyzed to a limited extent. This article focuses on the packaging waste stream generated in the construction sector. To this purpose current on-site waste packaging management has been assessed by monitoring ten Mediterranean residential building works. The findings of the experimental data collection revealed that the incentive measures implemented by the construction company to improve on-site waste sorting failed to achieve the intended purpose, showing low segregation ratios. Subsequently, through an analytical study the generation patterns for packaging waste are established, leading to the identification of the prevailing kinds of packaging and the products responsible for their generation. Results indicate that plastic waste generation maintains a constant trend throughout the whole construction process, while cardboard becomes predominant towards the end of the construction works with switches and sockets from the electricity stage. Understanding the production patterns of packaging waste will be beneficial for adapting waste management strategies to the identified patterns for the specific nature of packaging waste within the context of construction worksites.
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International Nuclear Information System (INIS)
González Pericot, N.; Villoria Sáez, P.; Del Río Merino, M.; Liébana Carrasco, O.
2014-01-01
Highlights: • On-site segregation level: 1.80%; training and motivation strategies were not effective. • 70% Cardboard waste: from switches and sockets during the building services stage. • 40% Plastic waste: generated during structures and partition works due to palletizing. • >50% Wood packaging waste, basically pallets, generated during the envelope works. - Abstract: The construction sector is responsible for around 28% of the total waste volume generated in Europe, which exceeds the amount of household waste. This has led to an increase of different research studies focusing on construction waste quantification. However, within the research studies made, packaging waste has been analyzed to a limited extent. This article focuses on the packaging waste stream generated in the construction sector. To this purpose current on-site waste packaging management has been assessed by monitoring ten Mediterranean residential building works. The findings of the experimental data collection revealed that the incentive measures implemented by the construction company to improve on-site waste sorting failed to achieve the intended purpose, showing low segregation ratios. Subsequently, through an analytical study the generation patterns for packaging waste are established, leading to the identification of the prevailing kinds of packaging and the products responsible for their generation. Results indicate that plastic waste generation maintains a constant trend throughout the whole construction process, while cardboard becomes predominant towards the end of the construction works with switches and sockets from the electricity stage. Understanding the production patterns of packaging waste will be beneficial for adapting waste management strategies to the identified patterns for the specific nature of packaging waste within the context of construction worksites
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Measurements of Mercury Released from Solidified/Stabilized Waste Forms
International Nuclear Information System (INIS)
Mattus, C.H.
2001-01-01
This report covers work performed during FY 1999-2000 in support of treatment demonstrations conducted for the Mercury Working Group of the U.S. Department of Energy (DOE) Mixed Waste Focus Area. In order to comply with the requirements of the Resource Conservation and Recovery Act, as implemented by the U.S. Environmental Protection Agency (EPA), DOE must use one of these procedures for wastes containing mercury at levels above 260 ppm: a retorting/roasting treatment or an incineration treatment (if the wastes also contain organics). The recovered radioactively contaminated mercury must then be treated by an amalgamation process prior to disposal. The DOE Mixed Waste Focus Area and Mercury Working Group are working with the EPA to determine if some alternative processes could treat these types of waste directly, thereby avoiding for DOE the costly recovery step. They sponsored a demonstration in which commercial vendors applied their technologies for the treatment of two contaminated waste soils from Brookhaven National Laboratory. Each soil was contaminated with ∼4500 ppm mercury; however, one soil had as a major radioelement americium-241, while the other contained mostly europium-152. The project described in this report addressed the need for data on the mercury vapor released by the solidified/stabilized mixed low-level mercury wastes generated during these demonstrations as well as the comparison between the untreated and treated soils. A related work began in FY 1998, with the measurement of the mercury released by amalgamated mercury, and the results were reported in ORNL/TM-13728. Four treatments were performed on these soils. The baseline was obtained by thermal treatment performed by SepraDyne Corp., and three forms of solidification/stabilization were employed: one using sulfur polymer cement (Brookhaven National Laboratory), one using portland cement [Allied Technology Group (ATG)], and a third using proprietary additives (Nuclear Fuel Services)
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Energy Technology Data Exchange (ETDEWEB)
Mora, Juan C., E-mail: jc.mora@ciemat.es [Unit for Radiation Protection of the Public and the Environment (PRPYMA), CIEMAT, Avda. Complutense, 40, 28040 Madrid (Spain); Energy Engineering Department, Power Engineering, Nuclear Area, ETSII, UNED (Spain); Baeza, Antonio [LARUEX, Dpt. Applied Physics, Faculty of Veterinary Science, University of Extremadura, Avda. Universidad, s/n, 10071 Cáceres (Spain); Robles, Beatriz [Unit for Radiation Protection of the Public and the Environment (PRPYMA), CIEMAT, Avda. Complutense, 40, 28040 Madrid (Spain); Sanz, Javier [Energy Engineering Department, Power Engineering, Nuclear Area, ETSII, UNED (Spain)
2016-06-05
Highlights: • Before 2010 NORM waste is managed as non-radioactive, disposed in landfills. • After 2010 radiological impact of the management of NORM wastes must be assessed. • Quantities that can be disposed in hazardous or non-hazardous landfills are given. • Uncertainty analysis is included to provide consistency to the calculations. - Abstract: Naturally Occurring Radioactive Materials (NORM) wastes are generated in huge quantities in several industries and their management has been carried out under considerations of industrial non-radioactive wastes, before the concern on the radioactivity content was included in the legislation. Therefore these wastes were conditioned using conventional methods and the waste disposals were designed to isolate toxic elements from the environment for long periods of time. Spanish regulation for these conventional toxic waste disposals includes conditions that assure adequate isolation to minimize the impact of the wastes to the environment in present and future conditions. After 1996 the radiological impact of the management of NORM wastes is considered and all the aspects related with natural radiations and the radiological control regarding the management of residues from NORM industries were developed in the new regulation. One option to be assessed is the disposal of NORM wastes in hazardous and non-hazardous waste disposals, as was done before this new regulation. This work analyses the management of NORM wastes in these landfills to derive the masses that can be disposed without considerable radiological impact. Generic dose assessments were carried out under highly conservative hypothesis and a discussion on the uncertainty and variability sources was included to provide consistency to the calculations.
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International Nuclear Information System (INIS)
Mora, Juan C.; Baeza, Antonio; Robles, Beatriz; Sanz, Javier
2016-01-01
Highlights: • Before 2010 NORM waste is managed as non-radioactive, disposed in landfills. • After 2010 radiological impact of the management of NORM wastes must be assessed. • Quantities that can be disposed in hazardous or non-hazardous landfills are given. • Uncertainty analysis is included to provide consistency to the calculations. - Abstract: Naturally Occurring Radioactive Materials (NORM) wastes are generated in huge quantities in several industries and their management has been carried out under considerations of industrial non-radioactive wastes, before the concern on the radioactivity content was included in the legislation. Therefore these wastes were conditioned using conventional methods and the waste disposals were designed to isolate toxic elements from the environment for long periods of time. Spanish regulation for these conventional toxic waste disposals includes conditions that assure adequate isolation to minimize the impact of the wastes to the environment in present and future conditions. After 1996 the radiological impact of the management of NORM wastes is considered and all the aspects related with natural radiations and the radiological control regarding the management of residues from NORM industries were developed in the new regulation. One option to be assessed is the disposal of NORM wastes in hazardous and non-hazardous waste disposals, as was done before this new regulation. This work analyses the management of NORM wastes in these landfills to derive the masses that can be disposed without considerable radiological impact. Generic dose assessments were carried out under highly conservative hypothesis and a discussion on the uncertainty and variability sources was included to provide consistency to the calculations.
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A step-by-step development of radioactive waste management strategy
International Nuclear Information System (INIS)
Lytsy, Tero; Yla-Mella, Mia
2013-01-01
Fennovoima is Finland's third nuclear power company founded in 2007. Fennovoima will build a new nuclear power plant, Hanhikivi 1, in Pyhajoki municipality located in Northern Finland. Currently Fennovoima is evaluating bids from reactor suppliers. Originally two suppliers, AREVA and Toshiba Heavy Industries were invited to bid for the plant but later also a bid from Rosatom were invited. The plant supplier will be selected in 2013. Platom is a Finnish company with extensive experience in radioactive waste management. In the beginning of 2008, Platom was assigned by Fennovoima as radioactive waste management consultant and to develop radioactive waste management strategy and to support Fennovoima in negotiations with plant suppliers in waste management aspects. Since Fennovoima has started, there have been some changes to the regulatory requirements which had to be taken into account while developing the strategy. One important change is due to the Government Degree 27.11.2008/736 which establishes a new waste category of very low-level waste following international development and the 'new' IAEA waste classification. Other important change was introduced by the change 342/2008 to the Nuclear Energy Act allowing some nuclear waste to be delivered to another country for treatment. These and many more requirements had to be considered when developing the strategy. Early work by Platom was mostly done to support development of application for Decision-in-Principle. This was the first important licensing step for Fennovoima. Work started with studies and plans which were used by Fennovoima to gather the know-how required to draw up the application. Descriptions of waste streams and waste management technologies were developed as well as preliminary waste inventories and studies for final disposal, including preliminary dimensioning of the repository facilities. Based on these plans nuclear regulator's preliminary safety assessment was performed. The
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Directory of Open Access Journals (Sweden)
Gábriel Györgyi T #336;ZSÉR
2010-01-01
Full Text Available Based on the regulations of Act XLIII/2000 on Waste Management to implement the strategic objectives and targets in the Act for the prevalence of the basic waste management principles a National Waste Management Plan II will be worked out and then accepted by the Parliament as part of the National Environmental Protection Programme. On the basis of the national plan the administrative bodies of environmental protection in accordance with the regional settlement and d evelopment programmes make a regional waste management project with the inclusion of the regional, local authorities, and other authorities concerned as well as the non governmental organisations for environmental protection. In our research we analyze the correlation between municipal solid waste per capita and urbanisation level. We have conducted similar calculations in the filed of population density and income. The study was carried out on a micro region level. Our analysis can help determine the framework conditions and factors that influence waste generation, and therefore should be taken into consideration when designing waste policies .
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Work plan for conducting an ecological risk assessment at J-Field, Aberdeen Proving Ground, Maryland
Energy Technology Data Exchange (ETDEWEB)
Hlohowskyj, I.; Hayse, J.; Kuperman, R. [Argonne National Lab., IL (United States). Environmental Assessment Div.] [and others
1995-03-01
The Environmental Management Division of Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation and feasibility study (RI/FS) of the J-Field area at APG pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. J-Field is within the Edgewood Area of APG in Harford County, Maryland, and activities at the Edgewood Area since World War II have included the development, manufacture, testing, and destruction of chemical agents and munitions. The J-Field site was used to destroy chemical agents and munitions by open burning and open detonation. This work plan presents the approach proposed to conduct an ecological risk assessment (ERA) as part of the RI/FS program at J-Field. This work plan identifies the locations and types of field studies proposed for each area of concern (AOC), the laboratory studies proposed to evaluate toxicity of media, and the methodology to be used in estimating doses to ecological receptors and discusses the approach that will be used to estimate and evaluate ecological risks at J-Field. Eight AOCs have been identified at J-Field, and the proposed ERA is designed to evaluate the potential for adverse impacts to ecological receptors from contaminated media at each AOC, as well as over the entire J-Field site. The proposed ERA approach consists of three major phases, incorporating field and laboratory studies as well as modeling. Phase 1 includes biotic surveys of the aquatic and terrestrial habitats, biological tissue sampling and analysis, and media toxicity testing at each AOC and appropriate reference locations. Phase 2 includes definitive toxicity testing of media from areas of known or suspected contamination or of media for which the Phase 1 results indicate toxicity or adverse ecological effects. In Phase 3, the uptake models initially developed in Phase 2 will be finalized, and contaminant dose to each receptor from all complete pathways will be estimated.
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Peristaltic pumps for waste disposal
International Nuclear Information System (INIS)
Griffith, G.W.
1992-09-01
Laboratory robots are capable of generating large volumes of hazardous liquid wastes when they are used to perform chemical analyses of metal finishing solutions. A robot at Allied-Signal Inc., Kansas City Division, generates 30 gallons of acid waste each month. This waste contains mineral acids, heavy metals, metal fluorides, and other materials. The waste must be contained in special drums that are closed to the atmosphere. The initial disposal method was to have the robot pour the waste into a collecting funnel, which contained a liquid-sensing valve to admit the waste into the drum. Spills were inevitable, splashing occurred, and the special valve often didn't work well. The device also occupied a large amount of premium bench space. Peristaltic pumps are made to handle hazardous liquids quickly and efficiently. A variable-speed pump, equipped with a quick-loading pump head, was mounted below the robot bench near the waste barrel. The pump inlet tube was mounted above the bench within easy reach of the robot, while the outlet tube was connected directly to the barrel. During operation, the robot brings the waste liquid up to the pump inlet tube and activates the pump. When the waste has been removed, the pump stops. The procedure is quick, simple, inexpensive, safe, and reliable
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International Nuclear Information System (INIS)
Kalb, P.D.; Colombo, P.
1983-01-01
The main objective of this study is to investigate new solidification agents relative to their potential application to wastes generated by advanced high volume reduction technologies, e.g., incinerator ash, dry solids, and ion exchange resins. Candidate materials selected for the solidification of these wastes include a modified sulfur cement and low-density polyethylene, neither of which are currently employed commerically for the solidification of low-level waste (LLW). As both the modified sulfur cement and the polyethylene are thermoplastic materials, a heated screw type extruder is utilized in the production of waste form samples for testing and evaluation. In this regard, work is being conducted to determine the range of conditions under which these solidification agents can be satisfactorily applied to the specific LLW streams and to provide information relevant to operating parameters and process control
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Energy Technology Data Exchange (ETDEWEB)
Henriksson, Gunilla
2010-07-01
In accordance with Sweden's environmental objectives it has been decided that, by 2010, 35 per cent of all food waste shall be recovered through biological treatment. In order to get there, the problems regarding collection methods needs to be solved. There are several different collection systems to choose between, but at the present time there is no complete list of the methods and techniques available on the market. Lists of advantages and disadvantages with each system, of potential improvements, and of completed or ongoing development projects are also missing, and creating difficulties for municipalities and businesses which are planning on introducing a system. The goal with this study is to provide a survey of technical problems with different systems and to identify previous studies as well as new innovations within collection techniques. The expectation is that this work eventually will lead to improved collection systems. The study will cover existing collection techniques in households, large-scale kitchens, restaurants and grocery stores in Sweden. The study will only cover the so called hard parameters, i.e. primarily technical issues. The target group is on the one hand municipalities planning on starting collection of food waste and on the other hand all actors in the area, such as innovators, producers and suppliers as well as Waste Refinery's organizations. Soft issues such as issues regarding information and quality are not included. The system limits of this project span between the recycling equipment of homes and businesses to the food waste's treatment at the biological treatment plant. The methods that have been used in this project are: questionnaire survey to 133 municipalities that today are recycling food waste, telephone interviews with a number of biological treatment plants and innovators in the business, and Internet searching for relevant reports and studies in the field. The results show that the paper bag and the
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Energy Technology Data Exchange (ETDEWEB)
Levin, V.
1994-04-01
Finding innovative ways to reduce waste streams generated at Department of Energy (DOE) sites by 50% by the year 2000 is a challenge for DOE`s waste minimization efforts. This report examines the usefulness of benchmarking as a waste minimization tool, specifically regarding common waste streams at DOE sites. A team of process experts from a variety of sites, a project leader, and benchmarking consultants completed the project with management support provided by the Waste Minimization Division EM-352. Using a 12-step benchmarking process, the team examined current waste minimization processes for liquid photographic waste used at their sites and used telephone and written questionnaires to find ``best-in-class`` industrv partners willing to share information about their best waste minimization techniques and technologies through a site visit. Eastman Kodak Co., and Johnson Space Center/National Aeronautics and Space Administration (NASA) agreed to be partners. The site visits yielded strategies for source reduction, recycle/recovery of components, regeneration/reuse of solutions, and treatment of residuals, as well as best management practices. An additional benefit of the work was the opportunity for DOE process experts to network and exchange ideas with their peers at similar sites.
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Spanish solid wastes legislation; Legislacion espanola de Residuos Solidos
Energy Technology Data Exchange (ETDEWEB)
Castrillon Pelaez, L.; Maranon Maison, E.; Rodriguez Iglesias
2001-07-01
A review is made of the regulations in the field of solid wastes with the aim of providing a useful working tool for those entities that generate or manage some type of waste. The coming into force of the current Spanish Wastes Law establishes common regulations for all wastes, substituting all previous Municipal Waste and Toxic and Dangerous Waste Laws. For reasons of greater practical applicability, we have preferred in this paper to classify wastes on the basis of their characteristics. The regulations are thus presented in a series of sections: municipal waste, dangerous wastes, sewage plant sludge, cattle waste and specific risk materials, highlighting in each case those areas of the regulations that are of greater interest for the producers and managers of solid wastes. (Author)
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Measurements of Mercury Released From Solidified/Stabilized Waste Forms-FY2002
International Nuclear Information System (INIS)
Mattus, C.H.
2003-01-01
This report covers work performed during FY 2002 in support of treatment demonstrations conducted for the U.S. Department of Energy (DOE) Mixed Waste Focus Area (MWFA) Mercury Working Group. To comply with the requirements of the Resource Conservation and Recovery Act, as implemented by the U.S. Environmental Protection Agency (EPA), DOE must use one of the following procedures for mixed low-level radioactive wastes containing mercury at levels above 260 ppm: a retorting/roasting treatment or (if the wastes also contain organics) an incineration treatment. The recovered radioactively contaminated mercury must then be treated by an amalgamation process prior to disposal. The DOE MWFA Mercury Working Group is working with EPA to determine whether some alternative processes could be used to treat these types of waste directly, thereby avoiding a costly recovery step for DOE. In previous years, demonstrations were performed in which commercial vendors applied their technologies for the treatment of radiologically contaminated elemental mercury as well as radiologically contaminated and mercury-contaminated waste soils from Brookhaven National Laboratory. The test results for mercury release in the headspace were reported in two reports, ''Measurements of Mercury Released from Amalgams and Sulfide Compounds'' (ORNL/TM-13728) and ''Measurements of Mercury Released from Solidified/Stabilized Waste Forms'' (ORNL/TM-2001/17). The current work did not use a real waste; a surrogate sludge had been prepared and used in the testing in an effort to understand the consequences of mercury speciation on mercury release
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Directory of Open Access Journals (Sweden)
Thelma Manning
2014-06-01
Full Text Available Cellulose acetate nitrate (CAN was used as an insensitive energetic binder to improve the insensitive munitions (IM properties of gun propellants to replace the M1 propellant used in 105 mm artillery charges. CAN contains the energetic nitro groups found in nitrocellulose (NC, but also acetyl functionalities, which lowered the polymer's sensitivity to heat and shock, and therefore improved its IM properties relative to NC. The formulation, development and small-scale characterization testing of several CAN-based propellants were done. The formulations, using insensitive energetic solid fillers and high-nitrogen modifiers in place of nitramine were completed. The small scale characterization testing, such as closed bomb testing, small scale sensitivity, thermal stability, and chemical compatibility were done. The mechanical response of the propellants under high-rate uni-axial compression at, hot, cold, and ambient temperatures were also completed. Critical diameter testing, hot fragment conductive ignition (HFCI tests were done to evaluate the propellants' responses to thermal and shock stimuli. Utilizing the propellant chemical composition, theoretical predictions of erosivity were completed. All the small scale test results were utilized to down-select the promising CAN based formulations for large scale demonstration testing such as the ballistic performance and fragment impact testing in the 105 mm M67 artillery charge configurations. The test results completed in the small and large scale testing are discussed.
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Colloidal agglomerates in tank sludge: Impact on waste processing
International Nuclear Information System (INIS)
Bunker, B.C.; Martin, J.E.
1998-01-01
'Insoluble colloidal sludges in hazardous waste streams such as tank wastes can pose serious problems for waste processing, interfering with retrieval, transport, separation, and solidification procedures. Properties of sediment layers and sludge suspensions such as slurry viscosities, sedimentation rates, and final sediment densities can vary by orders of magnitude depending on the particle types present, the degree to which the particles agglomerate or stick to each other, and on a wide range of processing parameters such as solution shear rates, pH, salt content, and temperature. The objectives of this work are to: (1) understand the factors controlling the nature and extent of colloidal agglomeration under expected waste processing conditions; (2) determine how agglomeration phenomena influence physical properties relevant to waste processing including rheology, sedimentation, and filtration; and (3) develop strategies for optimizing processing conditions via control of agglomeration phenomena. Insoluble colloidal sludges in hazardous waste streams such as tank wastes can pose serious problems for waste processing, interfering with retrieval, transport, separation, and solidification procedures. Properties of sediment layers and sludge suspensions such as slurry viscosities, sedimentation rates, and final sediment densities can vary by orders of magnitude depending on the particle types present, the degree to which the particles agglomerate or stick to each other, and on a wide range of processing parameters such as solution shear rates, pH, salt content, and temperature. The objectives of this work are to: (1) understand the factors controlling the nature and extent of colloidal agglomeration under expected waste processing conditions; (2) determine how agglomeration phenomena influence physical properties relevant to waste processing including rheology, sedimentation, and filtration; and (3) develop strategies for optimizing processing conditions via control
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The problem of industrial wastes
International Nuclear Information System (INIS)
Hamdan, Fouad
1998-01-01
The paper is the result of a feasibility study conducted for the Green peace Office in Lebanon. The overall goal of the study was to work towards implementing a national waste management plan and to combat the import of hazardous wastes from developing countries.The author focuses on the illegal trade of industrial wastes from developed to under developed countries. The trade of toxic wastes causes on environmental pollution. As for Lebanese industries, the main problem is toxic industrial wastes. About 4000 tones/day of domestic wastes are produced in Lebanon. 326000 tones of industrial wastes contain toxic substances are annually produced and wastes growth rate is expected to increase to one million tone/year in 2010. A disaster is threatening Lebanon especially that no policy were taken to deal with the huge growth of wastes. This problem affect on population health especially in the region of Bourj Hammoud. Analysis of ground water in the region of Chekka, confirm the existence of water pollution caused by toxic materials In addition, analysis of Petro coke used in the National Lebanese Cement Industry, contain a high rate of Polycyclic Aromatic Hydrocarbons. Green peace is aware of the danger of wastes in air, water and land pollution and preventing environment of any source of pollution this will certainly lead to a sustainable development of the country
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Waste management - sewage - special wastes
International Nuclear Information System (INIS)
1987-01-01
The 27 papers represent a cross-section of the subject waste management. Particular attention is paid to the following themes: waste avoidance, waste product utilization, household wastes, dumping technology, sewage sludge treatments, special wastes, seepage from hazardous waste dumps, radioactive wastes, hospital wastes, purification of flue gas from waste combustion plants, flue gas purification and heavy metals, as well as combined sewage sludge and waste product utilization. The examples given relate to plants in Germany and other European countries. 12 papers have been separately recorded in the data base. (DG) [de
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The AREVA's waste management strategy
International Nuclear Information System (INIS)
Poncet, Ph.
2011-01-01
In accordance with its policy of sustainable development and continuous progress, AREVA is permanently seeking to reduce the impact of the management of its waste, of whatever type, and its radioactive waste in particular. This goal is taken into consideration very early in industrial projects and concerns all the phases in the life of the installations and all the activities of the Group. The resulting actions aim to guarantee that an exhaustive inventory is made of the radioactive materials and waste, to optimise how they are characterised, to ensure their traceability and to determine the best management methods. Past and future progress relies primarily on the effectiveness of zoning (in particular the concept of radiological cleanness), how work is organized, the account taken of operating experience feedback, the search for recycling solutions or appropriate removal routes, optimisation of waste storage and, whenever possible, online processing, plus of course the professionalism of all those involved. A participatory approach by the Group will enable the focus areas and required actions to be defined: networks and multidisciplinary working groups, whenever possible in association with other stake-holders or partners from the nuclear industry. (author)
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International Nuclear Information System (INIS)
1992-01-01
This book highlights the main issues of public concern related to radioactive waste management and puts them into perspective. It provides an overview of radioactive waste management covering, among other themes, policies, implementation and public communication based on national experiences. Its purpose is to assists in increasing the understanding of radioactive waste management issues by public and national authorities, organizations involved in radioactive waste management and the nuclear industry; it may also serve as a source book for those who communicate with the public. Even in the unlikely event that nuclear power does not further develop around the world, the necessity for dealing with nuclear waste from past usages, from uranium mining and milling, decontamination and decommissioning of existing nuclear facilities and from the uses of radioactive materials in medicine, industry and research would still exist. In many countries, radioactive waste management planning involves making effective institutional arrangements in which responsibilities and liabilities are well established for the technical operation and long term surveillance of disposal systems. Financing mechanisms are part of the arrangements. Continuous quality assurance and quality control, at all levels of radioactive waste management, are essential to ensure the required integrity of the system. As with any other human activity, improvements in technology and economics may be possible and secondary problems avoided. Improvements and confirmation of the efficiency of processes and reduction of uncertainties can only be achieved by continued active research, development and demonstration, which are the goals of many national programmes. International co-operation, also in the form of reviews, can contribute to increasing confidence in the ongoing work. The problem of radioactive wastes is not a unique one; it may be compared with other problems of toxic wastes resulting from many other
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removal of hazardous pollutants from industrial waste solutions using membrane techniques
International Nuclear Information System (INIS)
Selim, Y.T.M.
2001-01-01
the removal of hazardous pollutants from industrial waste solutions is of essential demand field for both scientific and industrial work. the present work includes detailed studies on the possible use of membrane technology especially liquid emulsion membrane for the removal of hazardous pollutants such as; cadmium , cobalt , lead, copper and uranium from different industrial waste solution . this research can be applied for mixed waste problems. the work carried out in this thesis is presented in three main chapters, namely introduction, experimental and results and discussion
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Technological Proposals for Recycling Industrial Wastes for Environmental Applications
Directory of Open Access Journals (Sweden)
Isabel Romero-Hermida
2014-08-01
Full Text Available A two-fold objective is proposed for this research: removing hazardous and unpleasant wastes and mitigating the emissions of green house gasses in the atmosphere. Thus, the first aim of this work is to identify, characterize and recycle industrial wastes with high contents of calcium or sodium. This involves synthesizing materials with the ability for CO2 sequestration as preliminary work for designing industrial processes, which involve a reduction of CO2 emissions. In this regard, phosphogypsum from the fertilizer industry and liquid wastes from the green olive and bauxite industries have been considered as precursors. Following a very simple procedure, Ca-bearing phosphogypsum wastes are mixed with Na-bearing liquid wastes in order to obtain a harmless liquid phase and an active solid phase, which may act as a carbon sequestration agent. In this way, wastes, which are unable to fix CO2 by themselves, can be successfully turned into effective CO2 sinks. The CO2 sequestration efficiency and the CO2 fixation power of the procedure based on these wastes are assessed.
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Innovative technologies for managing oil field waste
International Nuclear Information System (INIS)
Veil, J.A.
2003-01-01
Each year, the oil industry generates millions of barrels of wastes that need to be properly managed. For many years, most oil field wastes were disposed of at a significant cost. However, over the past decade, the industry has developed many processes and technologies to minimize the generation of wastes and to more safely and economically dispose of the waste that is generated. Many companies follow a three-tiered waste management approach. First, companies try to minimize waste generation when possible. Next, they try to find ways to reuse or recycle the wastes that are generated. Finally, the wastes that cannot be reused or recycled must be disposed of. Argonne National Laboratory (Argonne) has evaluated the feasibility of various oil field waste management technologies for the U.S. Department of Energy. This paper describes four of the technologies Argonne has reviewed. In the area of waste minimization, the industry has developed synthetic-based drilling muds (SBMs) that have the desired drilling properties of oil-based muds without the accompanying adverse environmental impacts. Use of SBMs avoids significant air pollution from work boats hauling offshore cuttings to shore for disposal and provides more efficient drilling than can be achieved with water-based muds. Downhole oil/water separators have been developed to separate produced water from oil at the bottom of wells. The produced water is directly injected to an underground formation without ever being lifted to the surface, thereby avoiding potential for groundwater or soil contamination. In the area of reuse/recycle, Argonne has worked with Southeastern Louisiana University and industry to develop a process to use treated drill cuttings to restore wetlands in coastal Louisiana. Finally, in an example of treatment and disposal, Argonne has conducted a series of four baseline studies to characterize the use of salt caverns for safe and economic disposal of oil field wastes.
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International Nuclear Information System (INIS)
Anderson, D.R.; Boyer, D.G.; Rueegger, B.; Olivier, J.P.
1984-01-01
The NEA/OECD Seabed Working Group, a subcommittee of the Radioactive Waste Management Committee (whose present membership includes Canada, the CEC, the Federal Republic of Germany, France, Japan, the Netherlands, the United Kingdom and the USA), is addressing the questions of how best to utilize the resources of the ocean. Since the beginning of time, the oceans have been the 'garbage dumps' of the land masses. Erosional processes continuously tear down mountains and the land and move them into the oceans. Most of the elements in nuclear waste are chemically identical to those being eroded, cycled and deposited in the ocean. Could the ocean's geological formations be used for the disposal of these radioactive wastes. The Seabed Working Group is divided into eight task groups: System Analysis, Site Selection, Sediment and Rock, Engineering Studies, Biology, Physical Oceanography, Waste Form and Canister, and Institutional. Within each of the groups a set of predictive models is being developed, the appropriate properties acquired, and predictions made. Laboratory and in-situ field tests will be conducted to verify the accuracy of the model predictions. The model sections will then be combined into a systems model to yield an estimate of the feasibility, risk and cost of this waste disposal option. The results to date of the technical and environmental feasibility studies of seabed disposal appear to be leading to a conclusion that this is technically feasible. Institutional feasibility is just beginning to be considered. (author)
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International Nuclear Information System (INIS)
International Atomic Energy Agency WATRP Review Team.
1995-12-01
The IAEA has, through its Waste Management Assessment and Technical Review Programme (WATRP), evaluated policies and facilities related to management of radioactive waste in Norway. It is concluded that the Himdalen site, in combination with the chosen engineering concept, can be suitable for the storage and disposal of the relatively small amounts of Norwegian low and intermediate level waste
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Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.
This guide is Unit 4 of the four-part series, Science, Society, and America's Nuclear Waste, produced by the U.S. Department of Energy's Office Civilian Radioactive Waste Management. The goal of this unit is to explain how transportation, a geologic repository, and the multi-purpose canister will work together to provide short-term and long-term…
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Quantifying the transport impacts of domestic waste collection strategies.
McLeod, Fraser; Cherrett, Tom
2008-11-01
This paper models the effects of three different options for domestic waste collection using data from three Hampshire authorities: (i) joint working between neighbouring waste collection authorities; (ii) basing vehicles at waste disposal sites; and (iii) alternate weekly collection of residual waste and dry recyclables. A vehicle mileage savings of 3% was modelled for joint working, where existing vehicle allocations to depots were maintained, which increased to 5.9% when vehicles were re-allocated to depots optimally. Vehicle mileage was reduced by 13.5% when the collection rounds were based out of the two waste disposal sites rather than out of the existing depots, suggesting that the former could be the most effective place to keep vehicles providing that travel arrangements for the crews could be made. Alternate weekly collection was modelled to reduce vehicle mileage by around 8% and time taken by 14%, when compared with a typical scenario of weekly collection of residual and fortnightly collection of recyclable waste. These results were based on an assumption that 20% of the residual waste would be directly diverted into the dry recyclables waste stream.
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Quantifying the transport impacts of domestic waste collection strategies
International Nuclear Information System (INIS)
McLeod, Fraser; Cherrett, Tom
2008-01-01
This paper models the effects of three different options for domestic waste collection using data from three Hampshire authorities: (i) joint working between neighbouring waste collection authorities; (ii) basing vehicles at waste disposal sites; and (iii) alternate weekly collection of residual waste and dry recyclables. A vehicle mileage savings of 3% was modelled for joint working, where existing vehicle allocations to depots were maintained, which increased to 5.9% when vehicles were re-allocated to depots optimally. Vehicle mileage was reduced by 13.5% when the collection rounds were based out of the two waste disposal sites rather than out of the existing depots, suggesting that the former could be the most effective place to keep vehicles providing that travel arrangements for the crews could be made. Alternate weekly collection was modelled to reduce vehicle mileage by around 8% and time taken by 14%, when compared with a typical scenario of weekly collection of residual and fortnightly collection of recyclable waste. These results were based on an assumption that 20% of the residual waste would be directly diverted into the dry recyclables waste stream
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Radiation Effects in Nuclear Waste Materials
International Nuclear Information System (INIS)
Weber, William J.; Wang, Lumin; Hess, Nancy J.; Icenhower, Jonathan P.; Thevuthasan, Suntharampillai
2003-01-01
The objective of this project is to develop a fundamental understanding of radiation effects in glasses and ceramics, as well as the influence of solid-state radiation effects on aqueous dissolution kinetics, which may impact the performance of nuclear waste forms and stabilized nuclear materials. This work provides the underpinning science to develop improved glass and ceramic waste forms for the immobilization and disposition of high-level tank waste, excess plutonium, plutonium residues and scrap, other actinides, and other nuclear waste streams. Furthermore, this work is developing develop predictive models for the performance of nuclear waste forms and stabilized nuclear materials. Thus, the research performed under this project has significant implications for the immobilization of High-Level Waste (HLW) and Nuclear Materials, two mission areas within the Office of Environmental Management (EM). With regard to the HLW mission, this research will lead to improved understanding of radiation-induced degradation mechanisms and their effects on dissolution kinetics, as well as development of predictive models for waste form performance. In the Nuclear Materials mission, this research will lead to improvements in the understanding of radiation effects on the chemical and structural properties of materials for the stabilization and long-term storage of plutonium, highly-enriched uranium, and other actinides. The research uses plutonium incorporation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of alpha decay and beta decay on relevant glasses and ceramics. The research under this project has the potential to result in improved glass and ceramic materials for the stabilization and immobilization of high-level tank waste, plutonium residues and scraps, surplus weapons plutonium, highly-enriched uranium, other actinides, and other radioactive materials
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Radiation Effects in Nuclear Waste Materials
International Nuclear Information System (INIS)
Weber, William J.
2005-01-01
The objective of this project is to develop a fundamental understanding of radiation effects in glasses and ceramics, as well as the influence of solid-state radiation effects on aqueous dissolution kinetics, which may impact the performance of nuclear waste forms and stabilized nuclear materials. This work provides the underpinning science to develop improved glass and ceramic waste forms for the immobilization and disposition of high-level tank waste, excess plutonium, plutonium residues and scrap, other actinides, and other nuclear waste streams. Furthermore, this work is developing develop predictive models for the performance of nuclear waste forms and stabilized nuclear materials. Thus, the research performed under this project has significant implications for the immobilization of High-Level Waste (HLW) and Nuclear Materials, two mission areas within the Office of Environmental Management (EM). With regard to the HLW mission, this research will lead to improved understanding of radiation-induced degradation mechanisms and their effects on dissolution kinetics, as well as development of predictive models for waste form performance. In the Nuclear Materials mission, this research will lead to improvements in the understanding of radiation effects on the chemical and structural properties of materials for the stabilization and long-term storage of plutonium, highly-enriched uranium, and other actinides. The research uses plutonium incorporation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of alpha decay and beta decay on relevant glasses and ceramics. The research under this project has the potential to result in improved glass and ceramic materials for the stabilization and immobilization of high-level tank waste, plutonium residues and scraps, surplus weapons plutonium, highly-enriched uranium, other actinides, and other radioactive materials
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Solidification of radioactive waste in a cement/lime mixture
International Nuclear Information System (INIS)
Zhou, H.; Colombo, P.
1984-01-01
The suitability of a cement/lime mixture for use as a solidification agent for different types of wastes was investigated. This work includes studies directed towards determining the wasted/binder compositional field over which successful solidification occurs with various wastes and the measurement of some of the waste from properties relevant to evaluating the potential for the release of radionuclides to the environment. In this study, four types of low-level radioactive wastes were simulated for incorporation into a cement/lime mixture. These were boric acid waste, sodium sulfate wastes, aion exchange resins and incinerator ash. 7 references, 3 figures, 2 tables
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Research needs in cement-based waste forms
International Nuclear Information System (INIS)
McDaniel, E.W.; Spence, R.D.; Tallent, O.K.
1990-01-01
Cement-based waste forms are one of the most widely used waste disposal options, yet definitive knowledge of the fate of the waste species inside the waste form is lacking. A fundamental understanding of the chemistry and microstructure of the waste forms would lead to a better understanding of the mass transfer of the waste species, more confidence in predicting and extrapolating waste form performance, and design of better waste forms. Better and cheaper leach tests would lead to quicker and more cost effective screening of waste form alternatives. In addition, assessment of durability may be important to predicting waste form performance in the field. It should be noted that the research needs discussed in this report are from the perspective of investigators working in applied waste management areas, while the proposed investigations are fundamental or basic. Details as to experimental methods and tools to be used in achieving the objectives of the proposed are research beyond the scope of this paper and are better filled in by others. In broad terms, the research topics discussed are correlation of cement-based waste form physical properties to performance, waste-form fundamental chemistry and microstructure, and product performance testing
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Waste dislodging and conveyance testing summary and conclusions to date
International Nuclear Information System (INIS)
Rinker, M.W.; Hatchell, B.K.; Mullen, O.D.
1994-09-01
This document summarizes recent work performed by the Waste Dislodging and Conveyance technology development program to provide assistance with the retrieval of wastes from the Hanford single-shell tanks (SSTs). This work is sponsored by the Underground Storage Tank-Integrated Demonstration (UST-ID) Office with the U.S. Department of Energy (DOE) Office of Technology Development. A baseline technology of high-pressure water-jet dislodging and pneumatic conveyance integrated as a scarifier is proposed as a means of retrieval. The tests and studies described were performed to demonstrate that at least one robust technology exists that could be effectively used with low water-addition arm-based systems. These results are preliminary and do not represent an optimized baseline. The Waste Dislodging and Conveyance work thus far has demonstrated that waterjet mobilization and air conveyance can mobilize and convey SST waste simulants at the target rates while operating within the space envelope and the dynamic loading constraints of deployment devices. The recommended technologies are well proven in industrial applications and are quite robust, yet lightweight and relatively benign to the retrieval environment. The baseline approach has versatility to continuously dislodge and convey a broad range of waste forms, from hard wastes to soft sludge wastes. The approach also has the major advantage of being noncontact with the waste surface under normal operation
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Development of characterization methods applied to radioactive wastes and waste packages
International Nuclear Information System (INIS)
Guy, C.; Bienvenu, Ph.; Comte, J.; Excoffier, E.; Dodi, A.; Gal, O.; Gmar, M.; Jeanneau, F.; Poumarede, B.; Tola, F.; Moulin, V.; Jallu, F.; Lyoussi, A.; Ma, J.L.; Oriol, L.; Passard, Ch.; Perot, B.; Pettier, J.L.; Raoux, A.C.; Thierry, R.
2004-01-01
This document is a compilation of R and D studies carried out in the framework of the axis 3 of the December 1991 law about the conditioning and storage of high-level and long lived radioactive wastes and waste packages, and relative to the methods of characterization of these wastes. This R and D work has permitted to implement and qualify new methods (characterization of long-lived radioelements, high energy imaging..) and also to improve the existing methods by lowering detection limits and reducing uncertainties of measured data. This document is the result of the scientific production of several CEA laboratories that use complementary techniques: destructive methods and radiochemical analyses, photo-fission and active photonic interrogation, high energy imaging systems, neutron interrogation, gamma spectroscopy and active and passive imaging techniques. (J.S.)
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Electrical processes for liquid waste treatment
International Nuclear Information System (INIS)
Turner, A.D.; Bridger, N.J.; Junkison, A.R.; Pottinger, J.S.
1987-08-01
This report describes the development of electrical techniques for the treatment of liquid waste streams. Part I is concerned with solid/liquid separation and the demonstration of the electrokinetic thickening of flocs at inorganic membranes suitable for intermediate-level wastes and electrochemical cleaning of stainless steel microfilters and graphite ultrafilters. Part II describes work on the development of electrochemical ion exchange, particularly the use of inorganic absorption media and polarity reversal to enhance system selectivity. Work on the adsorption and desorption of plutonium in acid nitrate solution at various electrode materials is also included. (author)
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Directory of Open Access Journals (Sweden)
Gbemileke A. Ogunranti
2016-09-01
Full Text Available Purpose: The main objective of this study is to develop a model for solving the one dimensional cutting stock problem in the wood working industry, and develop a program for its implementation. Design/methodology/approach: This study adopts the pattern oriented approach in the formulation of the cutting stock model. A pattern generation algorithm was developed and coded using Visual basic.NET language. The cutting stock model developed is a Linear Programming (LP Model constrained by numerous feasible patterns. A LP solver was integrated with the pattern generation algorithm program to develop a one - dimensional cutting stock model application named GB Cutting Stock Program. Findings and Originality/value: Applying the model to a real life optimization problem significantly reduces material waste (off-cuts and minimizes the total stock used. The result yielded about 30.7% cost savings for company-I when the total stock materials used is compared with the former cutting plan. Also, to evaluate the efficiency of the application, Case I problem was solved using two top commercial 1D-cutting stock software. The results show that the GB program performs better when related results were compared. Research limitations/implications: This study round up the linear programming solution for the number of pattern to cut. Practical implications: From Managerial perspective, implementing optimized cutting plans increases productivity by eliminating calculating errors and drastically reducing operator mistakes. Also, financial benefits that can annually amount to millions in cost savings can be achieved through significant material waste reduction. Originality/value: This paper developed a linear programming one dimensional cutting stock model based on a pattern generation algorithm to minimize waste in the wood working industry. To implement the model, the algorithm was coded using VisualBasic.net and linear programming solver called lpsolvedll (dynamic
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Shifting paradigms in managing radioactive waste
International Nuclear Information System (INIS)
Le Bars, Y.; Pescatore, C.
2004-01-01
The Stakeholder involvement in policy making of radioactive waste management, has received considerable attention within the OECD. The Nea forum on Stakeholder confidence (FSC) was set up in 2000. A Nea recent publication entitled ''Learning and adapting to societal requirements for radioactive waste management'' brings together the key FSC findings and experience covering four years of work. Six main areas are targeted in this publication and are briefly described in this document: favourable candidates for issuing radioactive waste management policy, the design of the decision-making process, the social and ethical dimension, trust in the actors, Stakeholder involvement and the local dimension of radioactive waste management. (A.L.B.)
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Radioactive waste management in the VS military nuclear industry
International Nuclear Information System (INIS)
Kobal'chuk, O.V.; Kruglov, A.K.; Sokolova, I.D.; Smirnov, Yu.V.
1989-01-01
Organization and plans of radioactive waste management in the US military nuclear industry, determining transition from the policy of temporal waste storage to their final and safe disposal are presented. Programs of long-term management of high-level, transuranium and low-level wastes, the problems of the work financing and the structure of management activities related to the radioactive waste processing military nuclear industry enterprises are considered
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State Waste Discharge Permit application, 100-N Sewage Lagoon
International Nuclear Information System (INIS)
1994-06-01
As part of the Hanford Federal Facility Agreement and Consent Order negotiations (Ecology et al. 1994), the US Department of Energy, Richland Operations Office, the US Environmental Protection Agency, and the Washington State Department of Ecology agreed that liquid effluent discharges to the ground on the Hanford Site which affect groundwater or have the potential to affect groundwater would be subject to permitting under the structure of Chapter 173--216 (or 173--218 where applicable) of the Washington Administrative Code, the State Waste Discharge Permit Program. As a result of this decision, the Washington State Department of Ecology and the US Department of Energy, Richland Operations Office entered into Consent Order No. DE 91NM-177, (Ecology and DOE-RL 1991). This document constitutes the State Waste Discharge Permit application for the 100-N Sewage Lagoon. Since the influent to the sewer lagoon is domestic waste water, the State Waste Discharge Permit application for Public Owned Treatment Works Discharges to Land was used. Although the 100-N Sewage Lagoon is not a Public Owned Treatment Works, the Public Owned Treatment Works application is more applicable than the application for industrial waste water. The 100-N Sewage Lagoon serves the 100-N Area and other Hanford Site areas by receiving domestic waste from two sources. A network of sanitary sewer piping and lift stations transfers domestic waste water from the 100-N Area buildings directly to the 100-N Sewage Lagoon. Waste is also received by trucks that transport domestic waste pumped from on site septic tanks and holding tanks. Three ponds comprise the 100-N Sewage Lagoon treatment system. These include a lined aeration pond and stabilization pond, as well as an unlined infiltration pond. Both piped-in and trucked-in domestic waste is discharged directly into the aeration pond
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State-of-the-art report on radioactive waste disposal
International Nuclear Information System (INIS)
Larsson, A.
1989-01-01
In view of the considerable work required to develop repositories for radioactive waste, an extensive international co-operation has evolved within the area. The work has also engaged the IAEA to a great extent. The Agency has published a number of reports, covering different aspects of waste disposal. Following a recommendation by its Technical Review Committee on Underground Disposal (TRCUD) the Agency will publish a ''state-of-the-art'' report on radioactive waste disposal. The report is still in the preparation stage. In this article the principal subjects of the future report are discussed
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Application in the Nordic Countries of international radioactive waste recommendations
International Nuclear Information System (INIS)
1986-01-01
In the publication ''Report on the Applicability of International Radiation Protection Recommendations in the Nordic Countries'' published in 1976 the radiation protection authorities in Denmark, Finland, Iceland, Norway and Sweden expressed their agreement on the main principles of radiation protection. All aspects of radiation protection are covered in the recommendations. Since the recommendations were released new information on radioactive protection has been published e.g. by ICRP, IAEA and OECD/NEA and the radiation protection authorities have felt it necessary to make a revision of Chapter 21, Radioactive Waste, in the Recommendations of the Nordic Countries. Since 1982, a working group from the radiation protection authorities has been working on that revision. In this work the experience from national and international work has been incorporated. The new recommendations are divided into two main parts, one dealing with waste originating from the nuclear fuel cycle (nuclear waste) and one with waste from other sources (non-nuclear waste). These recommendations have been approved by the Nordic radiation protection authorities at a meeting in Finland, September 1985 and replace the corresponding recommendations in Chapter 21 in The 1976 Nordic Recommendations. (author)
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Optimization-based design of waste heat recovery systems
DEFF Research Database (Denmark)
Cignitti, Stefano
/or selected. This dissertation focuses on the chemical product and process systems used for waste heat recovery. Here, chemical products are working fluids, which are under continuous development and screening to fulfill regulatory environmental protection and safe operation requirements. Furthermore......, for the recovery of low-grade waste heat, new fluids and processes are needed to make the recovery technically and economically feasible. As the chemical product is influential in the design of the process system, the design of novel chemical products must be considered with the process system. Currently, state...... product and process system in terms of efficiency and sustainability. Today, some of the most important chemical product design problems are solvents and working fluids. Solvents are a vital part in the recovery of valuable resources in separation processes or waste water treatment. Working fluids...
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International Nuclear Information System (INIS)
2003-11-01
This issue contains 184 abstracts that describe research in progress in the field of radioactive waste management. The research abstracts contained in the Waste Management Research Abstracts Volume 28 (WMRA 28) were collected between October 1, 2002 and September 30, 2003. The abstracts reflect research in progress, or planned, in the field of radioactive waste management. They present ongoing work in various countries and international organizations. Although the abstracts are indexed by country, some programmes are actually the result of cooperation among several countries. Indeed, a primary reason for providing this compilation of programmes, institutions and scientists engaged in research into radioactive waste management is to increase international co-operation and facilitate communications
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Avoidable waste management costs
International Nuclear Information System (INIS)
Hsu, K.; Burns, M.; Priebe, S.; Robinson, P.
1995-01-01
This report describes the activity based costing method used to acquire variable (volume dependent or avoidable) waste management cost data for routine operations at Department of Energy (DOE) facilities. Waste volumes from environmental restoration, facility stabilization activities, and legacy waste were specifically excluded from this effort. A core team consisting of Idaho National Engineering Laboratory, Los Alamos National Laboratory, Rocky Flats Environmental Technology Site, and Oak Ridge Reservation developed and piloted the methodology, which can be used to determine avoidable waste management costs. The method developed to gather information was based on activity based costing, which is a common industrial engineering technique. Sites submitted separate flow diagrams that showed the progression of work from activity to activity for each waste type or treatability group. Each activity on a flow diagram was described in a narrative, which detailed the scope of the activity. Labor and material costs based on a unit quantity of waste being processed were then summed to generate a total cost for that flow diagram. Cross-complex values were calculated by determining a weighted average for each waste type or treatability group based on the volume generated. This study will provide DOE and contractors with a better understanding of waste management processes and their associated costs. Other potential benefits include providing cost data for sites to perform consistent cost/benefit analysis of waste minimization and pollution prevention (WMIN/PP) options identified during pollution prevention opportunity assessments and providing a means for prioritizing and allocating limited resources for WMIN/PP
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Avoidable waste management costs
Energy Technology Data Exchange (ETDEWEB)
Hsu, K.; Burns, M.; Priebe, S.; Robinson, P.
1995-01-01
This report describes the activity based costing method used to acquire variable (volume dependent or avoidable) waste management cost data for routine operations at Department of Energy (DOE) facilities. Waste volumes from environmental restoration, facility stabilization activities, and legacy waste were specifically excluded from this effort. A core team consisting of Idaho National Engineering Laboratory, Los Alamos National Laboratory, Rocky Flats Environmental Technology Site, and Oak Ridge Reservation developed and piloted the methodology, which can be used to determine avoidable waste management costs. The method developed to gather information was based on activity based costing, which is a common industrial engineering technique. Sites submitted separate flow diagrams that showed the progression of work from activity to activity for each waste type or treatability group. Each activity on a flow diagram was described in a narrative, which detailed the scope of the activity. Labor and material costs based on a unit quantity of waste being processed were then summed to generate a total cost for that flow diagram. Cross-complex values were calculated by determining a weighted average for each waste type or treatability group based on the volume generated. This study will provide DOE and contractors with a better understanding of waste management processes and their associated costs. Other potential benefits include providing cost data for sites to perform consistent cost/benefit analysis of waste minimization and pollution prevention (WMIN/PP) options identified during pollution prevention opportunity assessments and providing a means for prioritizing and allocating limited resources for WMIN/PP.
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PUREX facility preclosure work plan
International Nuclear Information System (INIS)
Engelmann, R.H.
1997-01-01
This preclosure work plan presents a description of the PUREX Facility, the history of the waste managed, and addresses transition phase activities that position the PUREX Facility into a safe and environmentally secure configuration. For purposes of this documentation, the PUREX Facility does not include the PUREX Storage Tunnels (DOE/RL-90/24). Information concerning solid waste management units is discussed in the Hanford Facility Dangerous Waste Permit Application, General Information Portion (DOE/RL-91-28, Appendix 2D)
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Affordable Rankine Cycle Waste Heat Recovery for Heavy Duty Trucks
Energy Technology Data Exchange (ETDEWEB)
Subramanian, Swami Nathan [Eaton Corporation
2017-06-30
Nearly 30% of fuel energy is not utilized and wasted in the engine exhaust. Organic Rankine Cycle (ORC) based waste heat recovery (WHR) systems offer a promising approach on waste energy recovery and improving the efficiency of Heavy-Duty diesel engines. Major barriers in the ORC WHR system are the system cost and controversial waste heat recovery working fluids. More than 40% of the system cost is from the additional heat exchangers (recuperator, condenser and tail pipe boiler). The secondary working fluid loop designed in ORC system is either flammable or environmentally sensitive. The Eaton team investigated a novel approach to reduce the cost of implementing ORC based WHR systems to Heavy-Duty (HD) Diesel engines while utilizing safest working fluids. Affordable Rankine Cycle (ARC) concept aimed to define the next generation of waste energy recuperation with a cost optimized WHR system. ARC project used engine coolant as the working fluid. This approach reduced the need for a secondary working fluid circuit and subsequent complexity. A portion of the liquid phase engine coolant has been pressurized through a set of working fluid pumps and used to recover waste heat from the exhaust gas recirculation (EGR) and exhaust tail pipe exhaust energy. While absorbing heat, the mixture is partially vaporized but remains a wet binary mixture. The pressurized mixed-phase engine coolant mixture is then expanded through a fixed-volume ratio expander that is compatible with two-phase conditions. Heat rejection is accomplished through the engine radiator, avoiding the need for a separate condenser. The ARC system has been investigated for PACCAR’s MX-13 HD diesel engine.
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Report on current research into organic materials in radioactive waste
International Nuclear Information System (INIS)
Norris, G.H.
1987-11-01
A preliminary review of relevant recent papers on organic materials in radioactive waste is presented. In particular, the effects of chelating or complexing agents, the influence of bacteria and the role of colloids are assessed. The requirement for further radioactive waste inventory detail is indicated. Potential problem areas associated with the presence of organic materials in radioactive waste are identified and appropriate experimental work to assess their significance is proposed. Recommendations for specific further work are made. A list and diagrams of some of the more important polymer structures likely to be present in radioactive waste and their possible degradation products are appended. (author)
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Radioactive waste storage and disposal: the challenge
International Nuclear Information System (INIS)
Prince, A.T.
1978-03-01
Solutions to waste management problems are available. After radium is removed, tailings from uranium ores can be disposed of safely in well-designed retention areas. Work is being done on the processing of non-fuel reactor wastes through incineration, reverse osmosis, and evaporation. Spent fuels have been stored safely for years in pools; dry storage in concrete cannisters is being investigated. Ultimate disposal of high-level wastes will be in deep, stable geologic formations. (LL)
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Energy Technology Data Exchange (ETDEWEB)
NONE
2012-07-15
The present Federal support concept is the basis for applied fundamental research concerning final disposal of heat generating radioactive wastes. The use-oriented fundamental research is aimed to the development of a scientific-technical basis for the realization of a final repository for heat-generating radioactive wastes and spent nuclear fuel, to the continuous advancement of the state of science and technology with respect to final waste disposal and a substantial contribution to the constitution, development and preservation of scientific-technological competence in the field of nuclear waste management in Germany. The concept includes research and development work concerning final disposal in the host rock salt, clays and crystalline rocks (granite). The research and development main issues are the final disposal system, the system behavior, further topics in relation to final disposal and nuclear materials surveillance.
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Waste analysis plan for confirmation or completion of Tank Farms backlog waste designation
International Nuclear Information System (INIS)
1993-08-01
This waste analysis plan satisfies the requirements of Item 3 of Ecology Order 93NM-201 as amended per the Settlement Agreement. Item 3 states: ''Within forty (40) calendar days of receipt of this Order, the US Department of Energy Richland Operations (DOE-RL) and Westinghouse Hanford Company (WHC) shall provide Ecology with a plan for review and approval detailing the established criteria and procedures for waste inspection, segregation, sampling, designation, and repackaging of all containers reported in item number-sign 1. The report shall include sampling plan criteria for different contaminated media, i.e., soils, compactable waste, high-efficiency particular air (HEPA) filters, etc., and a schedule for completing the work within the time allowed under this Order.'' Item 3 was amended per the Settlement Agreement as follows: ''In addition to the waste inspection plans for the ''unknowns'' previously provided and currently being supplemented, DOE-RL and WHC shall provide a draft waste analysis plan for the containers reported in Item 1 of the Order to Ecology by July 12, 1993. A final, DOE-RL approved waste analysis plan shall be submitted to Ecology by September 1, 1993, for Ecology's written approval by September 15, 1993.'' Containers covered by the Order, Settlement Agreement, and this waste analysis plan consist of all those reported under Item 1 of the Order, less any containers that have been identified in unusual occurrences reported by Tank Farms. This waste analysis plan describes the procedures that will be undertaken to confirm or to complete designation of the solid waste identified in the Order
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International Nuclear Information System (INIS)
De Stefanis, P.
1999-01-01
In this paper are reported analysis of some energy recovery form wastes plants. In this work are considered materials and energy flows, environmental impacts and related treatment costs and financial resources [it
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International Nuclear Information System (INIS)
Larsen, M.M.; Logan, J.A.
1984-05-01
EG and G Idaho, Inc., has established the Waste Experimental Reduction Facility (WERF) at the Idaho National Engineering Laboratory (INEL) to develop the capability to reduce the volume that low-level beta/gamma wastes occupy at the disposal site. The work effort at WERF includes a waste sizing development activity (WSDA), a waste melting development activity (WMDA), and a waste incineration development activity (WIDA). This report describes work and developments to date in the WSDA and WMDA with noncontaminated metallic waste in preparation for operations at WERF involving beta/gamma-contaminated metal
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PLUGGING AND UNPLUGGING OF WASTE TRANSFER PIPELINES
International Nuclear Information System (INIS)
Ebadian, M.A.
1999-01-01
This project, which began in FY97, involves both the flow loop research on plugging and unplugging of waste transfer pipelines, and the large-scale industrial equipment test of plugging locating and unplugging technologies. In FY98, the related work was performed under the project name ''Mixing, Settling, and Pipe Unplugging of Waste Transfer Lines.'' The mixing, settling, and pipeline plugging and unplugging are critical to the design and maintenance of a waste transfer pipeline system, especially for the High-Level Waste (HLW) pipeline transfer. The major objective of this work is to recreate pipeline plugging conditions for equipment testing of plug locating and removal and to provide systematic operating data for modification of equipment design and enhancement of performance of waste transfer lines used at DOE sites. As the waste tank clean-out and decommissioning program becomes active at the DOE sites, there is an increasing potential that the waste slurry transfer lines will become plugged and unable to transport waste slurry from one tank to another or from the mixing tank to processing facilities. Transfer systems may potentially become plugged if the solids concentration of the material being transferred increases beyond the capability of the prime mover or if upstream mixing is inadequately performed. Plugging can occur due to the solids' settling in either the mixing tank, the pumping system, or the transfer lines. In order to enhance and optimize the slurry's removal and transfer, refined and reliable data on the mixing, sampling, and pipe unplugging systems must be obtained based on both laboratory-scale and simulated in-situ operating conditions
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Management of radioactive waste in FR Yugoslavia
International Nuclear Information System (INIS)
Plecas, I.
1998-01-01
In the last forty years, in FR Yugoslavia, as a result of the two research reactors operation and as a result of the radionuclides application in the medicine, industry and agriculture, radioactive waste materials of different levels of specific activity was generated. As a temporary solution, these radioactive waste materials are stored in the two interim storage facilities. Since the one of the storages is completely filled with the radioactive waste materials that are packed in the metal drums and plastic barrels, and the second one has a effective space for radioactive waste materials storing for the approximately next few years, attempts are made in the 'Vinca' institute of nuclear sciences in developing the immobilization process for the low and intermediate level radioactive waste materials and their safe disposal into the appropriate disposal system, that was adopted for such materials. Research work on optimization of the chosen techniques in treatment, conditioning, immobilization and storing the radioactive waste materials is in progress. Investigations are carrying out on materials that are adopted as components of the engineer trench system, in aim to improve their physical-chemical properties, mainly retention the radionuclides release from the disposal facility to environment, as well as their mechanical characteristics. Parallel with the optimization of the composition of the materials that will create the engineer trench system, optimization of the processes and matrix-radioactive waste mixture forms is in progress, and we hope that this work will influence the design of the future Yugoslav storage center, shallow land burial type, for low and intermediate level radioactive waste materials
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Energy Technology Data Exchange (ETDEWEB)
Singhabhandhu, Ampaitepin; Tezuka, Tetsuo [Energy Economics Laboratory, Department of Socio-Environmental Energy Science, Graduate School of Energy Science, Kyoto University, Yoshida-honmachi, Sakyo-ku, Kyoto 606-8501 (Japan)
2010-06-15
Energy generation by wastes is considered one method of waste management that has the benefit of energy recovery. From the waste-to-energy point of view, waste cooking oil, waste lubricating oil, and waste plastics have been considered good candidates for feedstocks for energy conversion due to their high heating values. Compared to the independent management of these three wastes, the idea of co-processing them in integration is expected to gain more benefit. The economies of scale and the synergy of co-processing these wastes results in higher quality and higher yield of the end products. In this study, we use cost-benefit analysis to evaluate the integrated management scenario of collecting the three wastes and converting them to energy. We report the total heat of combustion of pyrolytic oil at the maximum and minimum conversion rates, and conduct a sensitivity analysis in which the parameters of an increase of the electricity cost for operating the process and increase of the feedstock transportation cost are tested. We evaluate the effects of economy of scale in the case of integrated waste management. We compare four cases of waste-to-energy conversion with the business as usual (BAU) scenario, and our results show that the integrated co-processing of waste cooking oil, waste lubricating oil, and waste plastics is the most profitable from the viewpoints of energy yield and economics. (author)
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Forest products decomposition in municipal solid waste landfills
International Nuclear Information System (INIS)
Barlaz, Morton A.
2006-01-01
Cellulose and hemicellulose are present in paper and wood products and are the dominant biodegradable polymers in municipal waste. While their conversion to methane in landfills is well documented, there is little information on the rate and extent of decomposition of individual waste components, particularly under field conditions. Such information is important for the landfill carbon balance as methane is a greenhouse gas that may be recovered and converted to a CO 2 -neutral source of energy, while non-degraded cellulose and hemicellulose are sequestered. This paper presents a critical review of research on the decomposition of cellulosic wastes in landfills and identifies additional work that is needed to quantify the ultimate extent of decomposition of individual waste components. Cellulose to lignin ratios as low as 0.01-0.02 have been measured for well decomposed refuse, with corresponding lignin concentrations of over 80% due to the depletion of cellulose and resulting enrichment of lignin. Only a few studies have even tried to address the decomposition of specific waste components at field-scale. Long-term controlled field experiments with supporting laboratory work will be required to measure the ultimate extent of decomposition of individual waste components
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Waste form development program. Annual report, October 1982-September 1983
International Nuclear Information System (INIS)
Colombo, P.; Kalb, P.D.; Fuhrmann, M.
1983-09-01
This report provides a summary of the work conducted for the Waste Form Development/Test Program at Brookhaven National Laboratory in FY 1983 under the sponsorship of the US Department of Energy's Low-Level Waste Management Program. The primary focus of this work is the investigation of new solidification agents which will provide improved immobilization of low-level radioactive wastes in an efficient, cost-effective manner. A working set of preliminary waste form evaluation criteria which could impact upon the movement of radionuclides in the disposal environment was developed. The selection of potential solidification agents for further investigation is described. Two thermoplastic materials, low-density polyethylene and a modified sulfur cement were chosen as primary candidates for further study. Three waste types were selected for solidification process development and waste form property evaluation studies which represent both new volume reduction wastes (dried evaporator concentrates and incinerator ash) and current problem wastes (ion exchange resins). Preliminary process development scoping studies were conducted to verify the compatibility of selected solidification agents and waste types and the potential for improved solidification. Waste loadings of 60 wt % Na 2 SO 4 , 25 wt % H 3 BO 3 , 25 wt % incinerator ash and 50 wt % dry ion exchange resin were achieved using low density polyethylene as a matrix material. Samples incorporating 65 wt % Na 2 SO 4 , 40 wt % H 3 BO 3 , 20 wt % incinerator ash and 40 wt % dry ion exchange resin were successfully solidified in modified sulfur cement. Additional improvements are expected for both matrix materials as process parameters are optimized. Several preliminary property evaluation studies were performed to provide the basis for an initial assessment of waste form acceptability. These included a two-week water immersion test and compressive load testing
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Mixed waste: The treatment of organic radioactive waste by means of adsorbents
International Nuclear Information System (INIS)
Sanhueza-Mir, A.; Morales-Galarce, T.
2001-01-01
Full text: The work described in this paper has been carried in the radioactive waste treatment facilities of the Nuclear Research Center Lo Aguirre, CEN LA, which are operated by Radioactive Waste Management Unit, UGDR. This last, centralizes its activities in order to manage all radioactive waste generated in the country due to the nuclear development. Features of danger and risks presented by organic radioactive liquid waste, make the need to develop a practicable alternative for its treatment and to allow the conditioning towards a suitable final disposal The raw material for this work, is an organic liquid waste arising from scintillation techniques, contaminated with Tritium. This mixed waste has to be treated and then conditioned in a solid form within a 200 I container, according with actual acceptance criteria for our temporary store for radioactive waste. The best formulation which allows to immobilize the liquid waste was determined. The first step consists in the adsorption treatment that waste is humbled. From the available adsorbents, two types were studied: adsorption granulat and diatomaceous earth. From the waste management standpoint, results with diatomaceous earth present physical characteristics better than the other Following, the second stage is the immobilization, which is achieved in a cement matrix made with puzzolanic cement (Polpaico 400) made in Chile. Later, due to cost and availability in the country, the diatomaceous earth is selected for the study, in the form of celite which is comparatively economic. The best mixture, with regard to physical feature, has the following composition: a 0.35 (w/w) water/cement ratio, which represents the needed quantity to obtain workability in the mixture, and it is the minimum amount of water to hydrating the cement; a waste/adsorbent ratio of 0.5 (v/v), in which the organic liquid is completely adsorbed and it is incorporated into the crystalline system of the solid form; and an adsorbed waste
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Coiner, R.L.; Pope, L.M.; Mehl, H.E.
2010-01-01
An assessment of energetic compounds (explosive and propellant residues) and associated semi-volatile organic compounds (SVOCs) and trace elements in streambed sediment and stream water from streams draining munitions firing points and impact areas at Fort Riley, northeast Kansas, was performed during 2007-08 by the U.S. Geological Survey (USGS) in cooperation with the U.S. Army. Streambed sediment from 16 sampling sites and stream-water samples from 5 sites were collected at or near Fort Riley and analyzed for as many as 17 energetic compounds, 65 SVOCs, and 27 trace elements. None of the energetic compounds or SVOCs were detected in streambed sediment collected from sites within the Fort Riley Military Reservation. This may indicate that these compounds either are not transported from dispersal areas or that analytical methods are not sensitive enough to detect the small concentrations that may be transported. Concentrations of munitions-associated trace elements did not exceed sediment-quality guidelines recommended by the U.S. Environmental Protection Agency (USEPA) and are not indicative of contamination of streambed sediment at selected streambed sampling sites, at least in regards to movement from dispersal areas. Analytical results of stream-water samples provided little evidence of contamination by energetic compounds, SVOCs, or associated trace elements. Perchlorate was detected in 19 of 20 stream-water samples at concentrations ranging from an estimated 0.057 to an estimated 0.236 ug/L (micrograms per liter) with a median concentration of an estimated 0.114 ug/L, substantially less than the USEPA Interim Health Advisory criterion (15 ug/L), and is in the range of documented background concentrations. Because of these small concentrations and possible natural sources (precipitation and groundwater), it is likely that the occurrence of perchlorate in stream water is naturally occurring, although a definitive identification of the source of perchlorate in
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Operating Procedures to Identify Wastes of Decommissioning
International Nuclear Information System (INIS)
Gatea, M.A.
2016-01-01
There are a number of sites in Iraq which have been used for nuclear activities and which contain potentially significant amounts of radioactive material. Many of these sites suffered substantial physical damage during the Gulf Wars as well as the challenging of the difficult security situation in the country.The destruction of the former nuclear facilities during the 1991 Gulf war aggravated the problem. As a result of these events, many of these nuclear facilities have lost their containment of the radioactive material and it now has an increased potential to be dispersed into the environment.Iraqi Decommissioning Directorate (IDD) is one of the Ministry of Science and Technology (MoST) formations. It deals with decommissioning of former Iraqi nuclear sites. It considers a producer of radioactive waste.Therefore, waste management represents the vital requirement to work accomplishment.The work carries out on-site waste pretreatment which considers as a minimization of waste management.W M is necessary to: Segregate 'at source' as much materials as possible to minimize quantities of radioactive waste, clear or exempt as much materials as possible and decontaminate and recycle as much radioactive waste as possible. And in more general terms: to control and account for radioactive waste to protect human health and the environment, to make sure we do not leave unnecessary burdens for future generations, to concentrate, contain and isolate the waste from the environment therefore, this make any releases to the environment to be restricted and subject to regulatory control.This procedure applies on-site waste pretreatment which comprises segregating, characterizing, minimizing, classifying, packaging and relocating of generated wastes during decommissioning of destroyed nuclear facilities. The stationary waste treatment activities are the responsibility of RWTD/MoST.The (RPC/MoE) is the national regulatory body during the whole radioactive waste management
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Electrochemical incineration of wastes
Kaba, L.; Hitchens, G. D.; Bockris, J. OM.
1989-01-01
The disposal of domestic organic waste in its raw state is a matter of increasing public concern. Earlier, it was regarded as permissible to reject wastes into the apparently infinite sink of the sea but, during the last 20 years, it has become clear that this is environmentally unacceptable. On the other hand, sewage farms and drainage systems for cities and for new housing developments are cumbersome and expensive to build and operate. New technology whereby waste is converted to acceptable chemicals and pollution-free gases at site is desirable. The problems posed by wastes are particularly demanding in space vehicles where it is desirable to utilize treatments that will convert wastes into chemicals that can be recycled. In this situation, the combustion of waste is undesirable due to the inevitable presence of oxides of nitrogen and carbon monoxide in the effluent gases. Here, in particular, electrochemical techniques offer several advantages including the low temperatures which may be used and the absence of any NO and CO in the evolved gases. Work done in this area was restricted to technological papers, and the present report is an attempt to give a more fundamental basis to the early stages of a potentially valuable technology.
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Characteristics of solidified high-level waste products
International Nuclear Information System (INIS)
1979-01-01
The object of the report is to contribute to the establishment of a data bank for future preparation of codes of practice and standards for the management of high-level wastes. The work currently in progress on measuring the properties of solidified high-level wastes is being studied
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Reuse of ground waste glass as aggregate for mortars.
Corinaldesi, V; Gnappi, G; Moriconi, G; Montenero, A
2005-01-01
This work was aimed at studying the possibility of reusing waste glass from crushed containers and building demolition as aggregate for preparing mortars and concrete. At present, this kind of reuse is still not common due to the risk of alkali-silica reaction between the alkalis of cement and silica of the waste glass. This expansive reaction can cause great problems of cracking and, consequently, it can be extremely deleterious for the durability of mortar and concrete. However, data reported in the literature show that if the waste glass is finely ground, under 75mum, this effect does not occur and mortar durability is guaranteed. Therefore, in this work the possible reactivity of waste glass with the cement paste in mortars was verified, by varying the particle size of the finely ground waste glass. No reaction has been detected with particle size up to 100mum thus indicating the feasibility of the waste glass reuse as fine aggregate in mortars and concrete. In addition, waste glass seems to positively contribute to the mortar micro-structural properties resulting in an evident improvement of its mechanical performance.
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Mixed Wastes Vitrification by Transferred Plasma
International Nuclear Information System (INIS)
Tapia-Fabela, J.; Pacheco-Pacheco, M.; Pacheco-Sotelo, J.; Torres-Reyes, C.; Valdivia-Barrientos, R.; Benitez-Read, J.; Lopez-Callejas, R.; Ramos-Flores, F.; Boshle, S.; Zissis, G.
2007-01-01
Thermal plasma technology provides a stable and long term treatment of mixed wastes through vitrification processes. In this work, a transferred plasma system was realized to vitrify mixed wastes, taking advantage of its high power density, enthalpy and chemical reactivity as well as its rapid quenching and high operation temperatures. To characterize the plasma discharge, a temperature diagnostic is realized by means of optical emission spectroscopy (OES). To typify the morphological structure of the wastes samples, scanning electron microscopy (SEM), and X-ray diffraction (XRD) techniques were applied before and after the plasma treatment
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Waste minimization in analytical methods
International Nuclear Information System (INIS)
Green, D.W.; Smith, L.L.; Crain, J.S.; Boparai, A.S.; Kiely, J.T.; Yaeger, J.S. Schilling, J.B.
1995-01-01
The US Department of Energy (DOE) will require a large number of waste characterizations over a multi-year period to accomplish the Department's goals in environmental restoration and waste management. Estimates vary, but two million analyses annually are expected. The waste generated by the analytical procedures used for characterizations is a significant source of new DOE waste. Success in reducing the volume of secondary waste and the costs of handling this waste would significantly decrease the overall cost of this DOE program. Selection of appropriate analytical methods depends on the intended use of the resultant data. It is not always necessary to use a high-powered analytical method, typically at higher cost, to obtain data needed to make decisions about waste management. Indeed, for samples taken from some heterogeneous systems, the meaning of high accuracy becomes clouded if the data generated are intended to measure a property of this system. Among the factors to be considered in selecting the analytical method are the lower limit of detection, accuracy, turnaround time, cost, reproducibility (precision), interferences, and simplicity. Occasionally, there must be tradeoffs among these factors to achieve the multiple goals of a characterization program. The purpose of the work described here is to add waste minimization to the list of characteristics to be considered. In this paper the authors present results of modifying analytical methods for waste characterization to reduce both the cost of analysis and volume of secondary wastes. Although tradeoffs may be required to minimize waste while still generating data of acceptable quality for the decision-making process, they have data demonstrating that wastes can be reduced in some cases without sacrificing accuracy or precision
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Degradation characteristics of waste polyurethane by radiation
Energy Technology Data Exchange (ETDEWEB)
Park, Jong Seok; Ahn, Sung Jun; Gwon Hui Jeong; Jeong, Sung In; Nho, Young Chang; Lim, Youn Mook [Research Division for Industry and Environment, Korea Atomic Energy Research Institute, Jeongeup (Korea, Republic of)
2017-06-15
Polyurethane (PU) is a very popular polymer that is used in a variety of applications due to its good mechanical, thermal, and chemical properties. However, waste PU recycling has received significant attention due to environmental issues. The aim of this work was to investigate the degradation characteristics of waste PU to recycle. Degradation of waste PU was carried out using a radiation techniques. Waste PUs were exposed to a gamma {sup 60}Co sources. To verify degradation, the irradiated PUs were characterized using FT-IR, gel permeation chromatography (GPC), and their thermal/mechanical properties are reported. When the radiation dose was 500 kGy, the molecular weight of the waste PU drastically decreased. Also, the mechanical properties of waste PU were approximately 4 times lower than those of non-irradiated PU. This study has confirmed the possibility of making fine particle of waste PU for recycling through radiation degradation techniques.