Product quality follow-up for the start of an industrial plant, e.g.: The waste station No 3 at La Hague

International Nuclear Information System (INIS)

Saas, A.; Vidal, H.; Alvy, J.C.; Boudry, J.C.; Bouin, R.

1990-01-01

During the start-up of the plant for waste treatment and mud coating in bitumen (waste station No 3 La Hague), the Characterization and Estimate of Containments and Analyses Service performed several different controls and tests to verify: whether the industrial plant was operating according to the defined procedure, whether the coated products obtained were in line with provisional specifications, whether the operational sector of the plant ensured the final quality of the coated product. The main results of these measurements and tests are presented in this paper. (orig./DG)

The economic impact of wasted prescription medication in an outpatient population of older adults.

Science.gov (United States)

Morgan, T M

2001-09-01

The causes and costs of outpatient medication waste are not known. We report the results of a cross-sectional pilot survey of medication waste in a convenience sample of 73 New Hampshire retirement community residents aged 65 years or older. We used questionnaires and in-home pill counts to determine the annual occurrence of medication waste, defined as no intention to take leftover medicines prescribed within the past year. Mean individual annual cost of wasted medication was $30.47 (range = $0-$131.56). Waste represented 2.3% of total medication costs. The main causes for waste included: resolution of the condition for which the medication was prescribed (37.4%), patient-perceived ineffectiveness (22.6%), prescription change by the physician (15.8%), and patient-perceived adverse effects (14.4%). Individual costs were modest, but if $30 per person represents a low estimate of average annual waste, the US national cost for adults older than 65 years would top $1 billion per year.

Start-up and operation strategies on the liquefied food waste anaerobic digestion and a full-scale case application.

Science.gov (United States)

Meng, Ying; Shen, Fei; Yuan, Hairong; Zou, Dexun; Liu, Yanping; Zhu, Baoning; Chufo, Akiber; Jaffar, Muhammad; Li, Xiujin

2014-11-01

Batch anaerobic digestion was employed to investigate the efficient start-up strategies for the liquefied food waste, and sequencing batch digestion was also performed to determine maximum influent organic loading rate (OLR) for efficient and stable operation. The results indicated that the start-up could be well improved using appropriate wastewater organic load and food-to-microorganism ratios (F/M). When digestion was initialized at low chemical oxygen demand (COD) concentration of 20.0 gCOD L(-1), the start-up would go well using lower F/M ratio of 0.5-0.7. The OLR 7.0 gCOD L(-1) day(-1) was recommended for operating the ASBR digestion, in which the COD conversion of 96.7 ± 0.53% and biomethane yield of 3.5 ± 0.2 L gCOD(-1) were achieved, respectively. The instability would occur when OLR was higher than 7.0 gCOD L(-1) day(-1), and this instability was not recoverable. Lipid was suggested to be removed before anaerobic digestion. The anaerobic digestion process in engineering project ran well, and good performance was achieved when the start-up and operational strategies from laboratory study were applied. For case application, stable digestion performance was achieved in a digester (850 m(3) volume) with biogas production of 1.0-3.8 m(3) m(-3) day(-1).

NCAW feed chemistry: Effect of starting chemistry on melter offgas and iron redox

International Nuclear Information System (INIS)

Smith, P.A.; Vienna, J.D.; Merz, M.D.

1995-03-01

The Pacific Northwest Laboratory (PNL) Vitrification Technology Development (PVTD) program has been established to develop technology to support immobilization of selected Hanford wastes. The effort of the PVTD program is directed by the U.S. Department of Energy (DOE). This report is part of the effort and focuses on the effect of starting waste chemistry on the vitrification process. The objective of the investigation was the evaluation of the effect of starting chemistry on the cold cap behavior in the vitrification of simulated neutralized current acid waste (NCAW). In addition this investigation provides an initial laboratory investigation of the cold cap and method for evaluation of alternate reductants

Clinical differences between younger and older adults with HIV/AIDS starting antiretroviral therapy in Uganda and Zimbabwe: a secondary analysis of the DART trial.

Directory of Open Access Journals (Sweden)

Sujal M Parikh

Full Text Available Clinical and immunological data about HIV in older adults from low and middle income countries is scarce. We aimed to describe differences between younger and older adults with HIV starting antiretroviral therapy in two low-income African countries.HIV clinics in Uganda and Zimbabwe.Secondary exploratory cross-sectional analysis of the DART randomized controlled trial.Clinical and laboratory characteristics were compared between adults aged 18-49 years (younger and ≥ 50 years (older, using two exploratory multivariable logistic regression models, one with HIV viral load (measured in a subset pre-ART and one without.A total of 3316 eligible participants enrolled in DART were available for analysis; 219 (7% were ≥ 50 years and 1160 (35% were male. Across the two adjusted regression models, older adults had significantly higher systolic blood pressure, lower creatinine clearance and were consistently less likely to be females compared to younger adults with HIV. Paradoxically, the models separately suggested that older adults had statistically significant (but not clinically important higher CD4+ cell counts and higher plasma HIV-1 viral copies at initiation. Crude associations between older age and higher baseline hemoglobin, body mass index, diastolic blood pressure and lower WHO clinical stage were not sustained in the adjusted analysis.Our study found clinical and immunological differences between younger and older adults, in a cohort of Africans starting antiretroviral therapy. Further investigations should explore how these differences could be used to ensure equity in service delivery and affect outcomes of antiretroviral therapy.

Brain tumor - primary - adults

Science.gov (United States)

... Vestibular schwannoma (acoustic neuroma) - adults; Meningioma - adults; Cancer - brain tumor (adults) ... Primary brain tumors include any tumor that starts in the brain. Primary brain tumors can start from brain cells, ...

A longitudinal study of systemic inflammation and recovery of lean body mass among malnourished HIV-infected adults starting antiretroviral therapy in Tanzania and Zambia

DEFF Research Database (Denmark)

PrayGod, George; Blevins, M; Woodd, Susannah

2016-01-01

BACKGROUND/OBJECTIVES: The effects of inflammation on nutritional rehabilitation after starting antiretroviral therapy (ART) are not well understood. We assessed the relationship between inflammation and body composition among patients enrolled in the Nutritional Support for African Adults Starting...... gains. Further studies are warranted to determine whether interventions to reduce systemic inflammation will enhance gains in fat-free mass.European Journal of Clinical Nutrition advance online publication, 20 January 2016; doi:10.1038/ejcn.2015.221....

Deep geological repository: Starting communication at potentially suitable sites

International Nuclear Information System (INIS)

Sumberova, Vera

2001-01-01

The siting of a deep geological repository in the Czech Republic is and will be a complicated process, since it is the first siting process of a nuclear facility designed from the start to be located at non-nuclear sites and to be organised under democratic conditions. This presentation describes the concept of radioactive waste and spent nuclear management in the Czech Republic, Communication activities of Radioactive Waste Repository Authority (RAWRA) with local representatives and lessons learned

Immobilization and Waste Form Product Acceptance for Low Level and TRU Waste Forms

International Nuclear Information System (INIS)

Holtzscheiter, E.W.; Harbour, J.R.

1998-05-01

The Tanks Focus Area is supporting technology development in immobilization of both High Level (HLW) and Low Level (LLW) radioactive wastes. The HLW process development at Hanford and Idaho is patterned closely after that of the Savannah River (Defense Waste Processing Facility) and West Valley Sites (West Valley Demonstration Project). However, the development and options open to addressing Low Level Waste are diverse and often site specific. To start, it is important to understand the breadth of Low Level Wastes categories

Waste audit pada industri penyamakan kulit

Directory of Open Access Journals (Sweden)

Prayitno Prayitno

1999-07-01

Full Text Available Waste audit is new environmental activities. to the Indonesia public and the large part of industrial community it is one of the environmental audit activities. Waste audit aims to identify whether the waste that by the industry waste so that metods for minimizing the waste can be found. In the leather tanning industry wasted audit is performend for every step pg the process, started from the raw material strage to the fishing ptocess.

Dioxins from medical waste incineration: Normal operation and transient conditions.

Science.gov (United States)

Chen, Tong; Zhan, Ming-xiu; Yan, Mi; Fu, Jian-ying; Lu, Sheng-yong; Li, Xiao-dong; Yan, Jian-hua; Buekens, Alfons

2015-07-01

Polychlorinated dibenzo-p-dioxins (PCDDs) and polychlorinated dibenzofurans (PCDFs) are key pollutants in waste incineration. At present, incinerator managers and official supervisors focus only on emissions evolving during steady-state operation. Yet, these emissions may considerably be raised during periods of poor combustion, plant shutdown, and especially when starting-up from cold. Until now there were no data on transient emissions from medical (or hospital) waste incineration (MWI). However, MWI is reputed to engender higher emissions than those from municipal solid waste incineration (MSWI). The emission levels in this study recorded for shutdown and start-up, however, were significantly higher: 483 ± 184 ng Nm(-3) (1.47 ± 0.17 ng I-TEQ Nm(-3)) for shutdown and 735 ng Nm(-3) (7.73 ng I-TEQ Nm(-3)) for start-up conditions, respectively. Thus, the average (I-TEQ) concentration during shutdown is 2.6 (3.8) times higher than the average concentration during normal operation, and the average (I-TEQ) concentration during start-up is 4.0 (almost 20) times higher. So monitoring should cover the entire incineration cycle, including start-up, operation and shutdown, rather than optimised operation only. This suggestion is important for medical waste incinerators, as these facilities frequently start up and shut down, because of their small size, or of lacking waste supply. Forthcoming operation should shift towards much longer operating cycles, i.e., a single weekly start-up and shutdown. © The Author(s) 2015.

Serum phosphate predicts early mortality in adults starting antiretroviral therapy in Lusaka, Zambia: a prospective cohort study.

Directory of Open Access Journals (Sweden)

Douglas C Heimburger

Full Text Available BACKGROUND: Patients starting antiretroviral therapy (ART for acquired immunodeficiency syndrome (AIDS in sub-Saharan Africa have high rates of mortality in the initial weeks of treatment. We assessed the association of serum phosphate with early mortality among HIV-infected adults with severe malnutrition and/or advanced immunosuppression. METHODOLOGY/PRINCIPAL FINDINGS: An observational cohort of 142 HIV-infected adults initiating ART in Lusaka, Zambia with body mass index (BMI <16 kg/m(2 or CD4(+ lymphocyte count <50 cells/microL, or both, was followed prospectively during the first 12 weeks of ART. Detailed health and dietary intake history, review of systems, physical examination, serum metabolic panel including phosphate, and serum ferritin and high-sensitivity C-reactive protein (hsCRP were monitored. The primary outcome was mortality. Baseline serum phosphate was a significant predictor of mortality; participants alive at 12 weeks had a median value of 1.30 mmol/L (interquartile range [IQR]: 1.04, 1.43, compared to 1.06 mmol/L (IQR: 0.89, 1.27 among those who died (p<0.01. Each 0.1 mmol/L increase in baseline phosphate was associated with an incremental decrease in mortality (AHR 0.83; 95% CI 0.72 to 0.95. The association was independent of other metabolic parameters and known risk factors for early ART-associated mortality in sub-Saharan Africa. While participant attrition represented a limitation, it was consistent with local program experience. CONCLUSIONS/SIGNIFICANCE: Low serum phosphate at ART initiation was an independent predictor of early mortality among HIV patients starting ART with severe malnutrition or advanced immunosuppression. This may represent a physiologic phenomenon similar to refeeding syndrome, and may lead to therapeutic interventions that could reduce mortality.

Hanford Site Waste management units report

International Nuclear Information System (INIS)

1992-01-01

This report summarizes the operable units in several areas of the Hanford Site Waste Facility. Each operable unit has several waste units (crib, ditch, pond, etc.). The operable units are summarized by describing each was unit. Some of the descriptions are unit name, unit type, waste category start data, site description, etc. The descriptions will vary for each waste unit in each operable unit and area of the Hanford Site

Malnutrition and associated factors among adults starting on ...

African Journals Online (AJOL)

user

This calls for routine nutritional assessment at CTCs prior to initiation of ART so as to ... exacerbates reduced food intake through hyperpyrexia, anorexia and thus leading to malnutrition. (WHO, 2003). ... adults and 6,000 children monthly.

Solid waste 30-year volume summary

International Nuclear Information System (INIS)

Valero, O.J.; Armacost, L.L.; DeForest, T.J.; Templeton, K.J.; Williams, N.C.

1994-06-01

A 30-year forecast of the solid waste volumes to be generated or received at the US Department of Energy Hanford Site is described in this report. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste that will require treatment, storage, and disposal at Hanford's Solid Waste Operations Complex (SWOC) during the 30-year period from FY 1994 through FY 2023. The data used to complete this document were collected from onsite and offsite waste generators who currently, or are planning to, ship solid wastes to the Hanford Site. An analysis of the data suggests that over 300,000 m 3 of LLMW and TRU/TRUM waste will be managed at Hanford's SWOC over the next 30 years. An extensive effort was made this year to collect this information. The 1993 solid waste forecast was used as a starting point, which identified approximately 100,000 m 3 of LLMW and TRU/TRUM waste to be sent to the SWOC. After analyzing the forecast waste volume, it was determined that additional waste was expected from the tank waste remediation system (TWRS), onsite decontamination and decommissioning (D ampersand D) activities, and onsite remedial action (RA) activities. Data presented in this report establish a starting point for solid waste management planning. It is recognized that forecast estimates will vary (typically increasing) as facility planning and missions continue to change and become better defined, but the information presented still provides useful insight into Hanford's future solid waste management requirements

Nuclear waste: Department of Energy's Transuranic Waste Disposal Plan needs revision

International Nuclear Information System (INIS)

1986-01-01

Transuranic waste consists of discarded tools, rags, machinery, paper, sheet metal, and glass containing man-made radioactive elements that can be dangerous if inhaled, ingested, or absorbed into the body through an open wound. GAO found that the Defense Waste Management Plan does not provide the Congress with complete inventory and cost data or details on environmental and safety issues related to the permanent disposal of TRU waste; the Plan's $2.8 billion costs are understated by at least $300 million. Further, it does not include costs for disposing of buried waste, contaminated soil, and TRU waste that may not be accepted at the Waste Isolation Pilot Plant. Lastly, the Plan provides no details on the environmental and safety issues related to the permanent disposal of TRU waste, nor does it discuss the types of or timing for environmental analyses needed before WIPP starts operating

How Hungary is Facing Waste Disposal Problem

International Nuclear Information System (INIS)

Ormai, P.; Frigyesi, F.; Gresits, I.; Solymosi, J.; Vincze, A.

1999-01-01

Management of radioactive waste of nuclear power plant origin comprises two main tasks: management of the high-level (spent fuel) and the low-and intermediate-level waste (LILW). With a plan to start operation of a repository for low-and intermediate-level waste (LILW) at the beginning of the next century, a site investigation programme was started in 1993. The site selection procedure. Between 1993-1995 some 300 geological objects were identified as potentially suitable for either near surface or tunnel-type disposal. The first stage of the site exploration has been performed and the decision on the continuation of the programme is due to by the end of 1998

Anaerobic co-digestion of animal waste: swine manure and tuna fish waste

Energy Technology Data Exchange (ETDEWEB)

Otero, L.; Alvarez, J. A.; Lema, J. M.

2009-07-01

Anaerobic digestion has become an established and proven technology for the treatment of solid wastes. Co-digestion offers several possible ecological, technology and economical advantages. Anaerobic co-digestion can increase CH{sub 4} production of manure diesters in a 50-200% according to the operation conditions and the co-substrates used. Last September 2007, PROBIOGAS project started up with the objective of improving the production and use of biogas from co-digestion of farming, agricultural and industrial waste. Our research group takes part in the study of co-digestion of swine manure firstly with tuna fish waste and secondly with glycerine (bio diesel production waste). (Author)

DOE states reheat nuclear waste debate

International Nuclear Information System (INIS)

Crawford, M.

1985-01-01

After decades of struggling with the issue, Congress in late 1982 established a firm plan for burying growing volumes of nuclear reactor wastes. But 2 l/2 years later the waste disposal debate is as hot as ever. Utility companies, environmentalists, federal officials, and state governments are again clashing - this time over the way the program is proceeding. The Nuclear Waste Policy Act calls for the Department of Energy to start accepting wastes in 1998 at the first of two planned repositories. Selection of this first repository site was mandated for early 1987, but program delays at DOE have pushed the decision back to March 1991. Despite this postponement and other schedule slips, the Department still aims to meet Congress's 1998 deadline. But states, Indian tribes, and environmentalists fear the site selection process will be compromised and want the start up date rolled back

Engineered waste-package-system design specification

International Nuclear Information System (INIS)

1983-05-01

This report documents the waste package performance requirements and geologic and waste form data bases used in developing the conceptual designs for waste packages for salt, tuff, and basalt geologies. The data base reflects the latest geotechnical information on the geologic media of interest. The parameters or characteristics specified primarily cover spent fuel, defense high-level waste, and commercial high-level waste forms. The specification documents the direction taken during the conceptual design activity. A separate design specification will be developed prior to the start of the preliminary design activity

Oklahoma City FILM Even Start Family Literacy Program Evaluation, 2000-2001.

Science.gov (United States)

Richardson, Donna Castle; Shove, Joanie; Brickman, Sharon; Terrell, Sherry; Shields, Jane

This report presents findings from the evaluation of the Oklahoma City Public Schools Even Start Program, also called the Family Intergenerational Literacy Model (FILM), now in its twelfth full year of operation. The evaluation focuses on the total population of adult students, preschoolers, adult graduates, and preschool graduates. The…

Public attitudes about nuclear waste

International Nuclear Information System (INIS)

Bisconti, A.S.

1991-01-01

There is general agreement that nuclear waste is an important national issue. It certainly is important to the industry. congress, too, gives high priority to nuclear waste disposal. In a recent pool by Reichman, Karten, Sword, 300 congressional staffers named nuclear waste disposal as the top nuclear energy-related legislative issue for Congress to address. In this paper most of the data the author discusses are from national polls that statistically represent the opinions of all American adults all across the country, as well as polls conducted in Nevada that statistically represent the opinions of all adults in that state. All the polls were by Cambridge Reports and have a margin of error of ± 3%

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

Sedimentary modelling and nuclear-waste disposal

International Nuclear Information System (INIS)

Van Loon, A.J.

1982-01-01

Nuclear energy is an important source of energy. Recently a slow down is experienced in its growth rate, due to the following factors: a) the supposed shortage of uranium; b) the fear for the consequences of nuclear accident, and c) the problem of nuclear wastes. Two types of waste are distinguished: a) fission products and actinides, and b) operational waste. The United States have started a program that must lead in 1989 to the first final storage of such waste in salt. Open-pit mines and oil-well drilling are discussed as possible solutions for operational waste storage

Evaluation of biogas of waste from poultry

International Nuclear Information System (INIS)

Lobo Paes, Juliana; Ferreira Matos, Camila; Souza Pereira, Diego José de; Bruggianesi, Giancarlo; Silva Misquita, Ícaro da

2015-01-01

Most of the farms, the waste of agricultural production do not receive adequate treatment for the stabilization of organic matter and reduce its pollution potential. The anaerobic digestion is an alternative for the treatment of waste, as well as allowing the reduction of pollution potential and the health risks of waste to a minimum, promotes the generation of biogas used as a heat source for various uses on the farm. Thus, the aim of this work was to evaluate the biogas production efficiency from the chicken waste. For the supply of biodigesters, adopted the total solids content of 8% and discontinuous supply system. The biogas potential was determined on the basis of their daily production and explosive rate. It was observed that the biogas production started 24 hours after the start of supplying the digesters. The maximum biogas production was approximately 0.87 L after the ninth and the 54th day starting the digestion process. The average daily production of biogas generated from bird manure was 0.022 L, while the cumulative 0.91 L after 72 days of digestion. The explosive rate of biogas generated by poultry origin residues peaked at 51% after 32 days of the start of the digestion process. In this analysis, we found the presence of methane in the biogas produced in all substrates tested after 24 h of digestion, because it’s burning in the presence of an ignition source (Fire). (full text)

Method of start-up operation of a liquefaction and distillation apparatus for processing waste gases containing radioactive rare gases

International Nuclear Information System (INIS)

Ota, Masakazu; Tani, Akira; Hashimoto, Hiroshi; An, Bunzai; Kanazawa, Toshio.

1975-01-01

Object: To enable reduction of cooling time, simplification of maintenance, and release of cooling gas outside system. Structure: In starting of the liquefaction and distillation apparatus, liquid nitrogen is introduced into the tower bottom of a rectification tower from a liquid nitrogen tank through a liquid nitrogen supply line to vaporize the liquid nitrogen with help of heat entered from outside and a heater. The vaporized nitrogen gas moves up while cooling the interior of the rectification tower and is guided by a vacuum pump from the top of tower toward the purifying gas line and low temperature heat exchanger and disharging into atmosphere. When the interior of the apparatus is sufficiently cooled in a manner as described above, the liquid nitrogen supply line is closed, the liquid nitrogen is fed to a condenser, and the waste gases containing the radioactive rare gases from the raw exhaust supply line are introduced into the rectification tower for entry of normal operation. (Kamimura, M.)

Protein-energy wasting and uremic failure to thrive in children with chronic kidney disease: they are not small adults.

Science.gov (United States)

Nourbakhsh, Noureddin; Rhee, Connie M; Kalantar-Zadeh, Kamyar

2014-12-01

Protein-energy wasting (PEW), a condition of decreased body protein and fat mass, is highly prevalent in patients with chronic kidney disease (CKD) and a potent predictor of mortality in this population. In adults with CKD, PEW has typically been defined on the basis of (1) deranged biochemical parameters, (2) reduced body mass, (3) reduced muscle mass, and (4) decreased dietary protein intake. Emerging data suggest that PEW may also commonly afflict children with CKD and have a negative impact on growth and development ("uremic failure to thrive"), yet it remains comparatively understudied and less well characterized in these patients. Given the challenges of applying adult-defined PEW criteria to the pediatric population, the authors of a recent study entitled "Protein energy wasting in children with chronic kidney disease" [Abraham et al. (2014) Pediatr Nephrol 29:1231-1238] have sought to develop a scoring system and three alterative definitions for this condition using a combination of biochemical markers, clinical measurements, and subjective reporting in children in the CKiD cohort: (1) minimal PEW definition (≥2 adult-defined PEW criteria); (2) standard PEW definition (≥3 adult-defined PEW criteria); (3) modified PEW definition (≥3 adult-defined PEW criteria, plus short stature or poor growth). These authors observed that meeting the modified PEW definition was associated with a significantly increased risk of hospitalization in unadjusted analyses, i.e., a 2.2-fold higher risk, and trended towards increased risk in multivariable adjusted analyses, i.e., 2.0-fold higher risk. At the present time, future studies validating these findings and developing further refined definitions and/or scoring systems for the detection and management of PEW in children and uremic failure to thrive are urgently needed.

Security of Radioactive Waste

International Nuclear Information System (INIS)

Goldammer, W.

2003-01-01

Measures to achieve radioactive waste security are discussed. Categorization of waste in order to implement adequate and consistent security measures based on potential consequences is made. The measures include appropriate treatment/storage/disposal of waste to minimize the potential and consequences of malicious acts; management of waste only within an authorised, regulated, legal framework; management of the security of personnel and information; measures to minimize the acquisition of radioactive waste by those with malicious intent. The specific measures are: deter unauthorized access to the waste; detect any such attempt or any loss or theft of waste; delay unauthorized access; provide timely response to counter any attempt to gain unauthorised access; measures to minimize acts of sabotage; efforts to recover any lost or stolen waste; mitigation and emergency plans in case of release of radioactivity. An approach to develop guidance, starting with the categorisation of sources and identification of dangerous sources, is presented. Dosimetric criteria for internal and external irradiation are set. Different exposure scenarios are considered. Waste categories and security categories based on the IAEA INFCIRC/225/Rev.4 are presented

Consumer-Related Food Waste

DEFF Research Database (Denmark)

Aschemann-Witzel, Jessica; Hooge, Ilona de; Normann, Anne

2016-01-01

Food waste has received increasing attention in recent years. As part of their corporate social responsibility strategies, food supply chain actors have started to act towards avoiding and reducing food waste. Based on a literature review, an expert interview study, and example cases, we discuss...... food marketing and the role and responsibility of retail. Food marketing and retailing contribute to consumer-related food waste via decisions on date labeling, packaging sizes and design elements, and pricing strategies encouraging overpurchase, as well as communication shifting consumer priorities...... to the disadvantage of food waste avoidance. Potential actions to tackle food waste relate to improved packaging and information, altering pricing strategies, and cooperation with other actors across the supply chain. Three cases highlight the extent to which moral and strategic motives are interlinked...

Separate collection of plastic waste, better than technical sorting from municipal solid waste?

Science.gov (United States)

Feil, Alexander; Pretz, Thomas; Jansen, Michael; Thoden van Velzen, Eggo U

2017-02-01

The politically preferred solution to fulfil legal recycling demands is often implementing separate collection systems. However, experience shows their limitations, particularly in urban centres with a high population density. In response to the European Union landfill directive, mechanical biological waste treatment plants have been installed all over Europe. This technology makes it possible to retrieve plastic waste from municipal solid waste. Operators of mechanical biological waste treatment plants, both in Germany and the Netherlands, have started to change their mechanical separation processes to additionally produce plastic pre-concentrates. Results from mechanical biological waste treatment and separate collection of post-consumer packaging waste will be presented and compared. They prove that both the yield and the quality of plastic waste provided as feedstock for the production of secondary plastic raw material are largely comparable. An economic assessment shows which conditions for a technical sorting plant are economically attractive in comparison to separate collection systems. It is, however, unlikely that plastic recycling will ever reach cost neutrality.

Summary of Waste Calcination at INTEC

Energy Technology Data Exchange (ETDEWEB)

O' Brien, Barry Henry; Newby, Bill Joe

2000-10-01

Fluidized-bed calcination at the Idaho Nuclear Technologies and Engineering Center (INTEC, formally called the Idaho Chemical Processing Plant) has been used to solidify acidic metal nitrate fuel reprocessing and incidental wastes wastes since 1961. A summary of waste calcination in full-scale and pilot plant calciners has been compiled for future reference. It contains feed compositions and operating conditions for all the processing campaigns for the original Waste Calcining Facility (WCF), the New Waste Calcining Facility (NWCF) started up in 1982, and numerous small scale pilot plant tests for various feed types. This summary provides a historical record of calcination at INTEC, and will be useful for evaluating calcinability of future wastes.

The low to intermediate activity and short living waste storage facility. For a controlled management of radioactive wastes

International Nuclear Information System (INIS)

2006-01-01

Sited at about 50 km of Troyes (France), the Aube facility started in 1992 and has taken over the Manche facility for the surface storage of low to intermediate and short living radioactive wastes. The Aube facility (named CSFMA) is the answer to the safe management of these wastes at the industrial scale and for 50 years onward. This brochure presents the facility specifications, the wastes stored at the center, the surface storage concept, the processing and conditioning of waste packages, and the environmental monitoring performed in the vicinity of the site. (J.S.)

Disposal of nuclear wastes

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

Abnormal glomerular filtration rate in children, adolescents and young adults starts below 75 mL/min/1.73 m(2).

Science.gov (United States)

Pottel, Hans; Hoste, Liesbeth; Delanaye, Pierre

2015-05-01

The chronic kidney disease (CKD) classification system for children is similar to that for adults, with both mainly based on estimated glomerular filtration rate (eGFR) combined with fixed cut-off values. The main cut-off eGFR value used to define CKD is 60 mL/min/1.73 m(2), a value that is also applied for children older than 2 years of age, adolescents and young adults. Based on a literature search, we evaluated inclusion criteria for eGFR in clinical trials or research studies on CKD for children. We also collected information on direct measurements of GFR (mGFR) in children and adolescents, with the aim to estimate the normal reference range for GFR. Using serum creatinine (Scr) normal reference values and Scr-based eGFR-equations, we also evaluated the correspondence between Scr normal reference values and (e)GFR normal reference values. Based on our literature search, the inclusion of children in published CKD studies has been based on cut-off values for eGFR of >60 mL/min/1.73 m(2). The lower reference limits for mGFR far exceed this adult threshold. Using eGFR values calculated using Scr-based formulas, we found that abnormal Scr levels in children already correspond to eGFR values that are below a cut-off of 75 mL/min/1.73 m(2). Abnormal GFR in children, adolescents and young adults starts below 75 mL/min/1.73 m(2), and as abnormality is a sign of disease, we recommend referring children, adolescents and young adults with an (e)GFR of <75 mL/min/1.73 m(2) for further clinical assessment.

Environmental issues and wastes

International Nuclear Information System (INIS)

Mitamura, Hisayoshi; Banba, Tsunetaka; Maeda, Toshikatsu; Ishiyama, Takashi

1999-08-01

All countries in the world are concerned about environmental issues because of their global effects. Developed industrial nations are also confronted with waste issues accompanied by mass production, mass consumption, and mass dump. We have reviewed books and reports to obtain a preliminary knowledge and to understand the trend of technology development before we start R and D for 'environmental monitoring, and environmental remediation and protection'. We lay great emphasis on municipal and industrial wastes in environmental issues and summarize the history of the earth, innovative environmental approaches in advanced nations, waste issues in Japan, and examples of technology development for environmental remediation and protection. (author)

Immobilization in ceramic waste forms of the residues from treatment of mixed wastes

International Nuclear Information System (INIS)

Oversby, V.M.; van Konynenburg, R.A.; Glassley, W.E.; Curtis, P.G.

1993-11-01

The Environmental Restoration and Waste Management Applied Technology Program at LLNL is developing a Mixed Waste Management Facility to demonstrate treatment technologies that provide an alternative to incineration. As part of that program, we are developing final waste forms using ceramic processing methods for the immobilization of the treatment process residues. The ceramic phase assemblages are based on using Synroc D as a starting point and varying the phase assemblage to accommodate the differences in chemistry between the treatment process residues and the defense waste for which Synroc D was developed. Two basic formulations are used, one for low ash residues resulting from treatment of organic materials contaminated with RCRA metals, and one for high ash residues generated from the treatment of plastics and paper products. Treatment process residues are mixed with ceramic precursor materials, dried, calcined, formed into pellets at room temperature, and sintered at 1150 to 1200 degrees C to produce the final waste form. This paper discusses the chemical composition of the waste streams and waste forms, the phase assemblages that serve as hosts for inorganic waste elements, and the changes in waste form characteristics as a function of variation in process parameters

The immobilisation of shredded waste in a cement matrix

International Nuclear Information System (INIS)

James, J.M.; Smith, D.L.

1985-10-01

Progress on the preparations for the encapsulation of plutonium contaminated shredded waste is summarised. Waste drums have been modified and filled with active shredded waste. Commissioning of the grout infilling test rig was started at the end of this period. Inactive process trials have continued in support of the design of the active encapsulation plant. (author)

ALTENER. Strategic framework municipal solid waste. Waste for energy network

International Nuclear Information System (INIS)

Kwant, K.W.; Van Halen, C.; Pfeiffer, A.E.

1997-01-01

General objective of European, national and regional waste for energy (WfE) policies is to support sustainable development. In each of the Altener WfE countries (Austria, Denmark, Finland, Italy, Netherlands, Portugal, Spain, Sweden and UK) general waste management strategies have been implemented. Common aspects are waste management hierarchies and general objectives such as: (1) to reduce the amount of wastes; (2) to make the best use of the wastes that are produced; and (3) to choose waste management practices, which (4) minimise the risks of immediate and future environmental pollution and harm to human health. All WfE countries have defined an order of preference for waste handling, starting with prevention as most preferred option, through re-use and recycling, thermal treatment with energy-recovery to landfill as a least desired option. In all Altener WfE countries, waste management structures are in a phase of transformation. At least three general transition processes can be recognized to take place, which are of great importance for the waste for energy future of the Altener countries: (1) increased energy recovery from MSW; (2) increased separation of MSW for recycling and recovery; and (3) reorganization of landfills. Two groups of instruments to stimulate the use of waste to energy are distinguished: (1) instruments, aiming to create improved WfE solutions; and (2) instruments, aiming to create a WfE market. In this framework document an overview is given of today's WfE situation in 9 European countries, as well as up-to-date national waste and energy policies, including the available instruments and future goals

Intelligent Information System for Waste Management; Jaetehuollon aelykaes tietojaerjestelmae iWaste

Energy Technology Data Exchange (ETDEWEB)

Mustonen, T. [Kuopio Univ. (Finland)

2003-07-01

'iWaste' is a project for developing and testing intelligent computational methods for more comprehensive waste management. Important issues are automated reporting, optimisation of waste collection, forecasting of waste formation, data handling of waste disposal sites and simulation and modelling of regional waste management. The main objective of the project is to identify and analyse known sources of information and to link them to the existing information processing systems in the field of waste management. Additionally, the goal is to identify and test functional elements that could be developed further to software products and services. The results of the project can be categorized into three sectors. Firstly, the guidelines for a comprehensive information system in waste management will be created. This includes the requirement specifications of different parties, definitions for the data exchange interfaces and an architectural plan for software products capable of co-operative processing. Secondly, the central parts of the intelligent information system will be piloted using the research database collected in the early stage of the project. The main topics investigated are data quality, the use of Geographical Information Systems (GIS), automated reporting, optimisation of waste collection and forecasting of waste formation. Additionally, the pilot information system can be utilized in derivative projects to speed up the starting phases of them. This makes it possible to create persistent development of waste management information systems both academically and commercially. (orig.)

Radioactive waste management: International peer reviews

International Nuclear Information System (INIS)

Warnecke, E.; Bonne, A.

1995-01-01

The Agency's peer review service for radioactive waste management - known as the Waste Management Assessment and Technical Review Programme (WATRP) - started in 1989, building upon earlier types of advisory programmes. WATRP's international experts today provide advice and guidance on proposed or ongoing radioactive waste management programmes; planning, operation, or decommissioning of waste facilities; or on legislative, organizational, and regulatory matters. Specific topics often cover waste conditioning, storage, and disposal concepts or facilities; or technical and other aspects of ongoing or planned research and development programmes. The missions can thus contributed to improving waste management systems and plans, and in raising levels of public confidence in them, as part of IAEA efforts to assist countries in the safe management of radioactive wastes. This article presents a brief overview of recent WATRP missions in Norway, Slovak Republic, Czech Republic and Finland

Concrete waste reduction of 50%

International Nuclear Information System (INIS)

Vos, R.M. de; Van der Wagt, K.M.; Van der Kruk, E.; Meeussen, H.W.

2016-01-01

During decommissioning quite a volume of concrete waste is produced. The degree of activation of the waste can range from clearly activated material to slightly activated or contaminated concrete. The degree of activation influences the applicable waste management processes that can be applied. The subsequent waste management processes can be identified for concrete waste are; disposal, segregation, re-use, conditional release and release. With each of these steps, the footprint of radioactive decommissioning waste is reduced. Future developments for concrete waste reduction can be achieved by applying smart materials in new build facilities (i.e. fast decaying materials). NRG (Nuclear Research and consultancy Group) has investigated distinctive waste management processes to reduce the foot-print of concrete waste streams resulting from decommissioning. We have investigated which processes can be applied in the Netherlands, both under current legislation and with small changes in legislation. We have also investigated the separation process in more detail. Pilot tests with a newly patented process have been started in 2015. We expect that our separation methods will reduce the footprint reduction of concrete waste by approximately 50% due to release or re-use in the nuclear sector or in the conventional industry. (authors)

WASTE PACKAGE TRANSPORTER DESIGN

International Nuclear Information System (INIS)

Weddle, D.C.; Novotny, R.; Cron, J.

1998-01-01

The purpose of this Design Analysis is to develop preliminary design of the waste package transporter used for waste package (WP) transport and related functions in the subsurface repository. This analysis refines the conceptual design that was started in Phase I of the Viability Assessment. This analysis supports the development of a reliable emplacement concept and a retrieval concept for license application design. The scope of this analysis includes the following activities: (1) Assess features of the transporter design and evaluate alternative design solutions for mechanical components. (2) Develop mechanical equipment details for the transporter. (3) Prepare a preliminary structural evaluation for the transporter. (4) Identify and recommend the equipment design for waste package transport and related functions. (5) Investigate transport equipment interface tolerances. This analysis supports the development of the waste package transporter for the transport, emplacement, and retrieval of packaged radioactive waste forms in the subsurface repository. Once the waste containers are closed and accepted, the packaged radioactive waste forms are termed waste packages (WP). This terminology was finalized as this analysis neared completion; therefore, the term disposal container is used in several references (i.e., the System Description Document (SDD)) (Ref. 5.6). In this analysis and the applicable reference documents, the term ''disposal container'' is synonymous with ''waste package''

Final repositories for high-level radioactive waste; Endlagerung hochradioaktiver Abfaelle

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-10-15

The brochure on final repositories for high-level radioactive waste covers the following issues: What is the origin of radioactive wastes? How large are the waste amounts? What is going to happen with the wastes? What is the solution for the Waste disposal? A new site search is started. Safety requirements for the final disposal of high-level radioactive wastes. Comparison of host rocks. Who is responsible and who will pay? Final disposal of high-level radioactive wastes worldwide. Short summary: History of the search for a final repository for high-level radioactive wastes in Germany.

Techno-economic feasibility of waste biorefinery

DEFF Research Database (Denmark)

Shahzad, Khurram; Narodoslawsky, Michael; Sagir, Muhammad

2017-01-01

elaborated a process for the production of polyhydroxyalkanoate (PHA) biopolymers starting from diverse waste streams of the animal processing industry. This article provides a detailed economic analysis of PHA production from this waste biorefinery concept, encompassing the utilization of low......-quality biodiesel, offal material and meat and bone meal (MBM). Techno-economic analysis reveals that PHA production cost varies from 1.41 €/kg to 1.64 €/kg when considering offal on the one hand as waste, or, on the other hand, accounting its market price, while calculating with fixed costs for the co...

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)

Radioisotope waste processing systems

International Nuclear Information System (INIS)

Machida, Tadashi

1978-01-01

The Atomic Energy Safety Bureau established the policy entitled ''On Common Processing System of Radioactive Wastes'' consulting with the Liaison Committee of Radioactive Waste Processing. Japan Atomic Energy Research Institute (JAERI) and Japan Radioisotope Association (JRIA) had been discussing the problems required for the establishment of the common disposal facilities based on the above policy, and they started the organization in spring, 1978. It is a foundation borrowing equipments from JAERI though installing newly some of them not available from JAERI, and depending the fund on JRIA. The operation expenses will be borne by those who want to dispose the wastes produced. The staffs are sent out from JAERI and JRIA. For animal wastes contaminated with RI, formaldehyde dipping should be abolished, but drying and freezing procedures will be taken before they are burnt up in a newly planned exclusive furnace with disposing capacity of 50 kg/hour. To settle the problems of other wastes, enough understanding and cooperation of users are to be requested. (Kobatake, H.)

Delayed Instructional Control of Head Start Children's Free Play.

Science.gov (United States)

Pierce, Charles H.; Risley, Todd R.

The free play of 5 black preschool Head Start children was observed. The variables manipulated in the study were delayed instructions and reinforcement for play with selected toys, and specific versus general instructions; the correspondence between the adult's instructions and reinforcement to the children's play was assessed. The data indicated…

Analysis on 3RWB model (Reduce, reuse, recycle, and waste bank) in comprehensive waste management toward community-based zero waste

Science.gov (United States)

Affandy, Nur Azizah; Isnaini, Enik; Laksono, Arif Budi

2017-06-01

Waste management becomes a serious issue in Indonesia. Significantly, waste production in Lamongan Regency is increasing in linear with the growth of population and current people activities, creating a gap between waste production and waste management. It is a critical problem that should be solved immediately. As a reaction to the issue, the Government of Lamongan Regency has enacted a new policy regarding waste management through a program named Lamongan Green and Clean (LGC). From the collected data, it showed that the "wet waste" or "organic waste" was approximately 63% of total domestic waste. With such condition, it can be predicted that the trashes will decompose quite quickly. From the observation, it was discovered that the generated waste was approximately 0.25 kg/person/day. Meanwhile, the number of population in Tumenggungan Village, Lamongan (data obtained from Monograph in Lamongan district, 2012) was 4651 people. Thus, it can be estimated the total waste in Lamongan was approximately 0.25 kg/person/day x 4651 characters = 930 kg/day. Within 3RWB Model, several stages have to be conducted. In the planning stage, the promotion of self-awareness among the communities in selecting and managing waste due to their interest in a potential benefit, is done. It indicated that community's awareness of waste management waste grew significantly. Meanwhile in socialization stage, each village staff, environmental expert, and policymaker should bear significant role in disseminating the awareness among the people. In the implementation phase, waste management with 3RWB model is promoted by applying it among of the community, starting from selection, waste management, until recycled products sale through the waste bank. In evaluation stage, the village managers, environmental expert, and waste managers are expected to regularly supervise and evaluate the whole activity of the waste management.

Solidification of Savannah River Plant high-level waste

International Nuclear Information System (INIS)

Maher, R.; Shafranek, L.F.; Stevens, W.R. III.

1983-01-01

The Department of Energy, in accord with recommendations from the Du Pont Company, has started construction of a Defense Waste Processing Facility (DWPF) at the Savannah River Plant. The facility should be completed by the end of 1988, and full-scale operation should begin in 1990. This facility will immobilize in borosilicate glass the large quantity of high-level radioactive waste now stored at the plant plus the waste to be generated from continued chemical reprocessing operations. The existing wastes at the Savannah River Plant will be completely converted by about 2010. 21 figures

TECHNICAL NOTE LIQUID WASTE DISPOSAL IN URBAN LOW ...

African Journals Online (AJOL)

In the ideal case the liquid waste can safely be disposed of in a properly designed and integrated network of pipes, which collect and transmit the liquid waste into a treatment plant. However, such a system is costly and needs a substantial amount of initial investment to start operating and subsequently to maintain.

Proceedings of the Task 2 workshop Waste Isolation Safety Assessment Program

International Nuclear Information System (INIS)

Bradley, D.J.

1979-01-01

The reports from the workshop on waste form release rate analysis are presented. The workshop started with overview presentations on the Office of Nuclear Waste Isolation (ONWI), the Waste Isolation Safety Assessment Program (WISAP), WISAP Task 2 (Waste Form Release Rate Analysis), and WISAP Task 4 (Sorption/Desorption Analysis). Technical presentations followed in these areas: leaching studies on spent fuels, leaching studies on high-level waste glass, waste form surface science experiments, radiation effects, and leach modeling. Separate abstracts were prepared for each

Proceedings of the Task 2 workshop Waste Isolation Safety Assessment Program

Energy Technology Data Exchange (ETDEWEB)

Bradley, D.J.

1979-01-01

The reports from the workshop on waste form release rate analysis are presented. The workshop started with overview presentations on the Office of Nuclear Waste Isolation (ONWI), the Waste Isolation Safety Assessment Program (WISAP), WISAP Task 2 (Waste Form Release Rate Analysis), and WISAP Task 4 (Sorption/Desorption Analysis). Technical presentations followed in these areas: leaching studies on spent fuels, leaching studies on high-level waste glass, waste form surface science experiments, radiation effects, and leach modeling. Separate abstracts were prepared for each.

Plasma technologies: applications to waste processing

International Nuclear Information System (INIS)

Fauchais, P.

2007-01-01

Since the 1990's, plasma technologies have found applications in the processing of toxic wastes of military and industrial origin, like the treatment of contaminated solids and low level radioactive wastes, the decontamination of soils etc.. Since the years 2000, this development is becoming exponential, in particular for the processing of municipal wastes and the recovery of their synthesis gas. The advantage of thermal plasmas with respect to conventional combustion techniques are: a high temperature (more than 6000 K), a pyrolysis capability (CO formation instead of CO 2 ), about 90% of available energy above 1500 K (with respect to 23% with flames), a greater energy density, lower gas flow rates, and plasma start-up and shut-down times of only few tenth of seconds. This article presents: 1 - the present day situation of thermal plasmas development; 2 - some general considerations about plasma waste processing; 3 - the plasma processes: liquid toxic wastes, solid wastes (contaminated soils and low level radioactive wastes, military wastes, vitrification of incinerators fly ash, municipal wastes processing, treatment of asbestos fibers, treatment of chlorinated industrial wastes), metallurgy wastes (dusts, aluminium slags), medical and ship wastes, perspectives; 4 -conclusion. (J.S.)

Prokaryotic diversity and dynamics in a full-scale municipal solid waste anaerobic reactor from start-up to steady-state conditions.

Science.gov (United States)

Cardinali-Rezende, Juliana; Colturato, Luís F D B; Colturato, Thiago D B; Chartone-Souza, Edmar; Nascimento, Andréa M A; Sanz, José L

2012-09-01

The prokaryotic diversity of an anaerobic reactor for the treatment of municipal solid waste was investigated over the course of 2 years with the use of 16S rDNA-targeted molecular approaches. The fermentative Bacteroidetes and Firmicutes predominated, and Proteobacteria, Actinobacteria, Tenericutes and the candidate division WWE1 were also identified. Methane production was dominated by the hydrogenotrophic Methanomicrobiales (Methanoculleus sp.) and their syntrophic association with acetate-utilizing and propionate-oxidizing bacteria. qPCR demonstrated the predominance of the hydrogenotrophic over aceticlastic Methanosarcinaceae (Methanosarcina sp. and Methanimicrococcus sp.), and Methanosaetaceae (Methanosaeta sp.) were measured in low numbers in the reactor. According to the FISH and CARD-FISH analyses, Bacteria and Archaea accounted for 85% and 15% of the cells, respectively. Different cell counts for these domains were obtained by qPCR versus FISH analyses. The use of several molecular tools increases our knowledge of the prokaryotic community dynamics from start-up to steady-state conditions in a full-scale MSW reactor. Copyright © 2012 Elsevier Ltd. All rights reserved.

Method of vitrificating fine-containing liquid waste

International Nuclear Information System (INIS)

Hagiwara, Minoru; Matsunaka, Kazuhisa.

1989-01-01

This invention concerns a vitrificating method of liquid wastes containing fines (metal powder discharged upon cutting fuel cans) used in a process for treating high level radioactive liquid wastes or a process for treating liquid wastes from nuclear power plants. Liquid wastes containing fines, slurries, etc. are filtered by a filter vessel comprising glass fibers. The fines are supplied as they are to a glass melting furnace placed in the vessel. Filterates formed upon filteration are mixed with other high level radioactive wastes and supplied together with starting glass material to the glass melting furnace. Since the fine-containing liquid wastes are processed separately from high radioactive liquid wastes, clogging of pipeways, etc. can be avoided, supply to the melting furnace is facilitated and the operation efficiency of the vitrification process can be improved. (I.N.)

JYT - Publicly financed nuclear waste management research programme

International Nuclear Information System (INIS)

Vuori, S.

1992-07-01

The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

JYT - Publicly financed nuclear waste management research programme

International Nuclear Information System (INIS)

Vuori, S.

1993-06-01

The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

JYT - Publicly financed nuclear waste management research programme

International Nuclear Information System (INIS)

Vuori, S.

1991-07-01

The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

WASTE PACKAGE TRANSPORTER DESIGN

Energy Technology Data Exchange (ETDEWEB)

D.C. Weddle; R. Novotny; J. Cron

1998-09-23

The purpose of this Design Analysis is to develop preliminary design of the waste package transporter used for waste package (WP) transport and related functions in the subsurface repository. This analysis refines the conceptual design that was started in Phase I of the Viability Assessment. This analysis supports the development of a reliable emplacement concept and a retrieval concept for license application design. The scope of this analysis includes the following activities: (1) Assess features of the transporter design and evaluate alternative design solutions for mechanical components. (2) Develop mechanical equipment details for the transporter. (3) Prepare a preliminary structural evaluation for the transporter. (4) Identify and recommend the equipment design for waste package transport and related functions. (5) Investigate transport equipment interface tolerances. This analysis supports the development of the waste package transporter for the transport, emplacement, and retrieval of packaged radioactive waste forms in the subsurface repository. Once the waste containers are closed and accepted, the packaged radioactive waste forms are termed waste packages (WP). This terminology was finalized as this analysis neared completion; therefore, the term disposal container is used in several references (i.e., the System Description Document (SDD)) (Ref. 5.6). In this analysis and the applicable reference documents, the term ''disposal container'' is synonymous with ''waste package''.

Bacterial leaching of waste uranium materials.

Science.gov (United States)

Barbic, F F; Bracilović, D M; Krajincanić, B V; Lucić, J L

1976-01-01

The effect of ferrobacteria and thiobacteria on the leaching of waste uranium materials from which 70-80% of uranium was previously leached by classical chemical hydrometallurgical procedure has been investigated. The bacteria used are found in the ore and the mine water of Zletovska River locality, Yugoslavia. Parameters of biological leaching were examined in the laboratory. Leaching conditions were changed with the aim of increasing the amount of uranium leached. The effect of pyrite added to the waste materials before the beginning of leaching has also been examined. Uranium leaching is directly proportional to the composition and number of ferrobacteria and thiobacteria, and increased by almost twice the value obtained from the same starting materials without using bacteria. Increased sulphuric acid concentrations stimulate considerably the rate of leaching. Uranium leaching is increased up to 20% while sulphuric acid consumption is simultaneously decreased by the addition of pyrite. Uranium concentrations in starting waste materials used for leaching were extremely low (0.0278 and 0.372% U) but about 60% recovery of uranium was obtained, with relatively low consumption of sulphuric acid.

Bacterial leaching of waste uranium materials

International Nuclear Information System (INIS)

Barbic, F.F.; Bracilovic, D.M.; Krajincanic, B.V.; Lucic, J.L.

1976-01-01

The effect of ferrobacteria and thiobacteria on the leaching of waste uranium materials from which 70-80% of uranium was previously leached by classical chemical hydrometallurgical procedure has been investigated. The bacteria used are found in the ore and the mine water of Zletovska River locality, Yugoslavia. Parameters of biological leaching were examined in the laboratory. Leaching conditions were changed with the aim of increasing the amount of uranium leached. The effect of pyrite added to the waste materials before the beginning of leaching has also been examined. Uranium leaching is directly proportional to the composition and number of ferrobacteria and thiobacteria, and increased by almost twice the value obtained from the same starting materials without using bacteria. Increased sulphuric acid concentrations stimulate considerably the rate of leaching. Uranium leaching is increased up to 20% while sulphuric acid consumption is simultaneously decreased by the addition of pyrite. Uranium concentrations in starting waste materials used for leaching were extremely low (0.0278 and 0.0372% U) but about 60% recovery of uranium was obtained, with relatively low consumption of sulphuric acid. (author)

Repository documentation rethought. A comprehensive approach from untreated waste to waste packages for final disposal

Energy Technology Data Exchange (ETDEWEB)

Anthofer, Anton Philipp; Schubert, Johannes [VPC GmbH, Dresden (Germany)

2017-11-15

The German Act on Reorganization of Responsibility for Nuclear Disposal (Entsorgungsuebergangsgesetz (EntsorgUebG)) adopted in June 2017 provides the energy utilities with the new option of transferring responsibility for their waste packages to the Federal Government. This is conditional on the waste packages being approved for delivery to the Konrad final repository. A comprehensive approach starts with the dismantling of nuclear facilities and extends from waste disposal and packaging planning to final repository documentation. Waste package quality control measures are planned and implemented as early as in the process qualification stage so that the production of waste packages that are suitable for final deposition can be ensured. Optimization of cask and loading configuration can save container and repository volume. Workflow planning also saves time, expenditure and exposure time for personnel at the facilities. VPC has evaluated this experience and developed it into a comprehensive approach.

Smaller plates, less food waste

DEFF Research Database (Denmark)

Hansen, Pelle Guldborg; Schmidt, Karsten; Skov, Laurits Rhoden

With roughly one-third of food produced for human consumption lost or wasted globally (about 1.3 billion tons per year), the impact on the environment cannot be anymore neglected. Actions at all points in the production chain are now urgent, including reductions in food waste at home, by retailers...... the hypothesis that dishware size plays an important role in the amount of food wasted among Danish adults in a self-service eating setting. This finding has PHN implications: slight changes in the foodscape can contribute to sustainable food consumption goals....

Historical perspective, economic analysis, and regulatory analysis of the impacts of waste partitioning-transmutation on the disposal of radioactive wastes

International Nuclear Information System (INIS)

Forsberg, C.W.; Croff, A.G.; Kocher, D.C.

1990-10-01

Partitioning-transmutation, sometimes called actinide burning, is an alternative approach to high-level radioactive waste management. It consists of removing long-lived radionuclides from wastes and destroying those radionuclides, thus reducing the long-term hazards of radioactive waste. It was studied in detail in the 1970's. New developments in technology and other factors are resulting in a reexamination of this waste management option. This report consists of three papers which summarize the historical work, update the analysis of the costs of waste disposal, and describe current regulatory requirements which might be impacted by P-T. The papers provide a starting point for future research on P-T. 152 refs., 2 figs., 19 tabs

All-cause mortality in HIV-positive adults starting combination antiretroviral therapy: correcting for loss to follow-up.

Science.gov (United States)

Anderegg, Nanina; Johnson, Leigh F; Zaniewski, Elizabeth; Althoff, Keri N; Balestre, Eric; Law, Matthew; Nash, Denis; Shepherd, Bryan E; Yiannoutsos, Constantin T; Egger, Matthias

2017-04-01

To estimate mortality in HIV-positive patients starting combination antiretroviral therapy (ART) and to discuss different approaches to calculating correction factors to account for loss to follow-up. A total of 222 096 adult HIV-positive patients who started ART 2009-2014 in clinics participating in the International epidemiology Databases to Evaluate AIDS collaboration in 43 countries in sub-Saharan Africa, Asia Pacific, Latin America, and North America were included. To allow for underascertainment of deaths due to loss to follow-up, two correction factors (one for the period 0-6 months on ART and one for later periods) or 168 correction factors (combinations of two sexes, three time periods after ART initiation, four age groups, and seven CD4 groups) based on tracing patients lost in Kenya and data linkages in South Africa were applied. Corrected mortality rates were compared with a worst case scenario assuming all patients lost to follow-up had died. Loss to follow-up differed between regions; rates were lowest in central Africa and highest in east Africa. Compared with using two correction factors (1.64 for the initial ART period and 2.19 for later), applying 168 correction factors (range 1.03-4.75) more often resulted in implausible mortality rates that exceeded the worst case scenario. Corrected mortality rates varied widely, ranging from 0.2 per 100 person-years to 54 per 100 person-years depending on region and covariates. Implausible rates were less common with the simpler approach based on two correction factors. The corrected mortality rates will be useful to international agencies, national programmes, and modellers.

Successful characterization of radioactive waste at the Savannah River Site

International Nuclear Information System (INIS)

Hughes, M.B.; Miles, G.M.

1995-01-01

Characterization of the low-level radioactive waste generated by forty five independent operating facilities at The Savannah River Site (SRS) experienced a slow start. However, the site effectively accelerated waste characterization based on findings of an independent assessment that recommended several changes to the existing process. The new approach included the development of a generic waste characterization protocol and methodology and the formulation of a technical board to approve waste characterization. As a result, consistent, detailed characterization of waste streams from SRS facilities was achieved in six months

Radioactive waste incineration system cold demonstration test, (2)

Energy Technology Data Exchange (ETDEWEB)

Hozumi, Masahiro; Seike, Yasuhiko; Takaoku, Yoshinobu; Yamanaka, Yasuhiro; Asahara, Masaharu; Katagiri, Keishi; Matsumoto, Kenji; Nagae, Madoka

1985-12-01

It is urgently necessary to solve the radioactive waste problem. As an effective means for the volume reduction of low-level radioactive wastes, an improved incineration system is greatly required. SHI's Waste Incineration (WIS) licensed by Combustion Engineering, Inc., has the significant advantage of processing a variety of wastes. We started a cold demonstration test in April, 1984 to verify the excellent performance of WIS. The test was successfully completed in September, 1985 with the record of more than 1000 hours of incineration testing time. In the present paper, we describe the test results during one and half years of test period.

Radioactive wastes: a reason to go against nuclear?

International Nuclear Information System (INIS)

Dupont, Jean-Francois

2013-01-01

In this note, the author aims at explaining the nature of the risk related to radioactive wastes, how these wastes are managed, and precautions which are taken for them not to be ever dangerous for mankind or for the environment. He discusses the safety aspects of separation of wastes from the biosphere, describes how radioactive wastes are separated from the biosphere, compares with the case of special wastes. Then he discusses and denies the various objections which are made regarding wastes and their management, i.e.: it is not acceptable nor ethical to pass on toxic wastes to several generations, there is no solution to the problem of radioactive wastes, the solution is bad or its reliability is not certain, the waste issue has been neglected from the start by people who do not care of humanist or ethical issues, people are afraid of deep geological storage

Bacterial population of piggery-waste anaerobic digesters

Energy Technology Data Exchange (ETDEWEB)

Hobson, P N; Shaw, B G

1974-08-01

A survey was made of the anaerobic and facultatively anaerobic bacteria present in piggery waste, digesting piggery waste and domestic anaerobic sludge used to start a piggery waste digester. An influence of the input waste was shown in that streptococci, the predominant facultatively anaerobic bacteria in the piggery waste, were the predominant bacteria in the digesting waste, and they replaced Entrobacter, predominant in the domestic sludge, when a piggery waste digestion had been established from this latter material. Cellulolytic or methanogenic bacteria could not be detected in the piggery waste but populations of these, and other hydrolytic bacteria, became established at different times during the build-up of digestion by gradual addition of piggery waste to water. The bacteria concerned in degradation of the waste constituents were all anaerobes. Production of methane from H/sub 2//CO/sub 2/, formate and butyrate could be detected in mixed cultures from dilutions of digester contents, but the only methanogenic bacterium that could be isolated in pure culture was Methanobacterium formicicum, which uses H/sub 2//CO/sub 2/ or formate only.

Measurement of volatile organic compounds during start-up of bioremediation of French limited superfund site in Crosby Texas using wind dependent whole-air sampling

International Nuclear Information System (INIS)

Pleil, J.D.; Fortune, C.R.; Yoong, M.; Oliver, K.D.

1993-01-01

Whole-air sampling was performed before and after the start-up of the bioremediation of an industrial (primarily petrochemical) waste lagoon in Crosby Texas, near Houston. Four 'Sector Samplers' were deployed at the four corners of the French Limited Superfund Site. These samplers collect air into one of two SUMMA polished canisters depending upon wind direction and speed. When the wind blows at the sampler from across the waste lagoon, air is routed to the 'IN' sector canister, otherwise sample is collected in the 'OUT' sector canister. As such, each sampler provides its own background sample, and, upon gas chromatographic analysis, individual compounds can be associated with the waste lagoon. Five sets of 24-hour sector samples were taken; the first set was collected prior to the start of the bioremediation effort and the remaining four sets were taken sequentially for four 24-hour periods after the start-up of the procedure

Nuclear Waste Fund management

International Nuclear Information System (INIS)

Mills, L.

1984-01-01

The Nuclear Waste Policy Acts requires that DOE enter into contracts with nuclear utilities and others to accept their nuclear wastes at some unspecified date, at some unspecified rate, hopefully starting in 1998. Contracts between DOE and the states, and with civilian and other government agencies must be sufficiently detailed to secure competitive bids on definable chunks of work at a fixed-cost basis with incentives. The need is stressed for a strong central program for the selection of contractors on the basis of competitive bidding on a fixed price basis to perform the task with defined deliverables

Plastic solidification of radioactive wastes

International Nuclear Information System (INIS)

Moriyama, Noboru

1981-01-01

Over 20 years have elapsed after the start of nuclear power development, and the nuclear power generation in Japan now exceeds the level of 10,000 MW. In order to meet the energy demands, the problem of the treatment and disposal of radioactive wastes produced in nuclear power stations must be solved. The purpose of the plastic solidification of such wastes is to immobilize the contained radionuclides, same as other solidification methods, to provide the first barrier against their move into the environment. The following matters are described: the nuclear power generation in Japan, the radioactive wastes from LWR plants, the position of plastic solidification, the status of plastic solidification in overseas countries and in Japan, the solidification process for radioactive wastes with polyethylene, and the properties of solidified products, and the leachability of radionuclides in asphalt solids. (J.P.N.)

Hospital waste management status in Lebanon

International Nuclear Information System (INIS)

Karam, R.; Oueida, F.; Tissot-Guerraz, F.; Trepo, D.; Collombel, C.

2000-01-01

author.The existing management of hospital waste in Lebanon currently poses both an environmental hazard as well as a public health risk. This is due mainly to lack of legislation, information and modern treatment and disposal facilities designed for this purpose. A nation-wide questionnaire survey was conducted to asses the status of hospital waste management. The study started from October 1997 till August 1998. We found that 75% of the surveyed hospitals completely ignore their total waste quantity: 73% of hospitals surveyed practice segregation at source of infectious, pathological, sharps and pharmaceuticals; more than 40% dispose of their hospital risk wastes through the municipality waste disposal, 24% by burning in open fires, 14% by on-site hospital incinerators, 11% in on-site dumping, 8% handled by a private contractor and 1% in uncontrolled landfill. We conclude that with some exceptions, the hospital waste management situation in Lebanon is very far from being satisfactory and therefore needs to be reconsidered. 1 Fig., 6 tabs., 18 refs

Influence of feed/inoculum ratios and waste cooking oil content on the mesophilic anaerobic digestion of food waste.

Science.gov (United States)

Li, Yangyang; Jin, Yiying; Borrion, Aiduan; Li, Jinhui

2018-03-01

Information on the anaerobic digestion (AD) of food waste (FW) with different waste cooking oil contents is limited in terms of the effect of the initial substrate concentrations. In this work, batch tests were performed to evaluate the combined effects of waste cooking oil content (33-53%) and feed/inoculum (F/I) ratios (0.5-1.2) on biogas/methane yield, process stability parameters and organics reduction during the FW AD. Both waste cooking oil and the inoculation ratios were found to affect digestion parameters during the AD process start-up and the F/I ratio was the predominant factor affecting AD after the start-up phase. The possible inhibition due to acidification caused by volatile fatty acids accumulation, low pH values and long-chain fatty acids was reversible. The characteristics of the final digestate indicated a stable anaerobic system, whereas samples with F/I ratios ranging from 0.8 to 1.2 display higher propionic and valeric acid contents and high amounts of total ammonia nitrogen and free ammonia nitrogen. Overall, F/I ratios higher than 0.70 caused inhibition and resulted in low biogas/methane yields from the FW. Copyright © 2018 Elsevier Ltd. All rights reserved.

Outline of the radioactive waste management strategy at the national radioactive waste disposal facility 'Ekores'

International Nuclear Information System (INIS)

Rozdyalovskaya, L.F.; Tukhto, A.A.; Ivanov, V.B.

2000-01-01

The national Belarus radioactive waste disposal facility 'Ekores' was started in 1964 and was designed for radioactive waste coming from nuclear applications in industry, medicine and research. It is located in the neighbourhood of Minsk (2 Mil. people) and it is the only one in this country. In 1997 the Government initiated the project for the facility reconstruction. The main reconstruction goal is to upgrade radiological safety of the site by creating adequate safety conditions for managing radioactive waste at the Ekores disposal facility. This covers modernising technologies for new coming wastes and also that the wastes currently disposed in the pits are retrieved, sorted and treated in the same way as new coming wastes. The reconstruction project developed by Belarus specialists was reviewed by the IAEA experts. The main provisions of the revised project strategy are given in this paper. The paper's intention is to outline the technical measures which may be taken at standard 'old type Soviet Radon' disposal facility so as to ensure the radiological safety of the site. (author)

Radioactive waste management policy and its implementation in the German Democratic Republic

International Nuclear Information System (INIS)

Sitzlack, G.

1988-01-01

Waste management is considered an integral part of measures for the safe utilization of nuclear energy. In the German Democratic Republic, back in 1962 the government established the National Board for Nuclear Safety and Radiation Protection as a special body whose regulatory responsibilities include the setting up of an appropriate waste management policy for the country's nuclear power programme. After studies started in the 1960s a central system for the collection and disposal of low- and intermediate-level radioactive wastes from nuclear power plants and other sources throughout the country was established, this started operation a few years ago. The waste repository is a reconstructed salt mine which is operated by the main waste producer - the nuclear power plant utility. There are no current issues with high-level waste, as the spent fuels are stored for many years and then returned to the supplier country, the Soviet Union. The paper describes the relevant regulatory framework in the German Democratic Republic. The solution established here takes future nuclear power uses into account. (author)

Method of solidifying and disposing radioactive waste plastic

International Nuclear Information System (INIS)

Matsuura, Hiroyuki; Yasumura, Keijiro

1981-01-01

Purpose: To solidify radioactive waste as it is with plastic by forming a W/O (Water-in-Oil) emulsion with the radioactive waste and a plastic solidifier, and treating it with a polymerization starting agent, an accelerator, and the like. Method: A predetermined amount of alkaline substance such as sodium hydroxide, triethanol, or the like is added quantitatively to radioactive waste and it is mixed by an agitator. A predetermined amount of solidifier such as unsaturated polyester or the like is added to the mixture and it is further mixed by the agitator to form a stable W/O emulsion. Subsequently, predetermined amounts of polymerization starting agent such as methyl ethyl ketone peroxide and polymerization accelerator such as cobalt naphthenate or the like are added thereto, the mixture is mixed, and is then allowed to stand for at room temperature for the plastic solidification thereof. No reaction occurs after the solidification. (Sekiya, K.)

WASTE MANAGEMENT AT SRS - MAKING IT HAPPEN

International Nuclear Information System (INIS)

Heenan, T. F.; Kelly, S.

2002-01-01

The past five years have witnessed a remarkable transition in the pace and scope of waste management activities at SRS. At the start of the new M and O contract in 1996, little was being done with the waste generated at the site apart from storing it in readiness for future treatment and disposal. Large volumes of legacy waste, particularly TRU and Low Level Waste, had accumulated over many years of operation of the site's nuclear facilities, and the backlog was increasing. WSRC proposed the use of the talents of the ''best in class'' partners for the new contract which, together with a more commercial approach, was expected to deliver more results without a concomitant increase in cost. This paper charts the successes in the Solid Waste arena and analyzes the basis for success

Present situation and issues for the French radioactive waste management agency

International Nuclear Information System (INIS)

Dupuis, M.C.

2009-01-01

This series of slides makes a status of the radioactive waste management in France: 1 - Planned disposal facilities: A - Low level long lived waste (LL-LL: Graphite Waste And Radium Bearing Waste): Implementation within a shallow clay formation (between 15 and 200 m in depth). For graphite waste: a 'repository with an intact cover' as a reference option. For radium-bearing waste: a 'repository with a reworked cover' under investigation. The required footprint on ground surface is in the order of 100 ha. Siting approach: June 2, 2008: letter from the Minister of State to the Chairman of ANDRA; June 2008: file addressed by ANDRA to the mayors of 3,115 communes. Until the end of October 2008: expression of interest by local communities. Possibility to confirm their application in late 2010. December 2008: assessment report by ANDRA and proposal of ranked zones to the government. Beginning of 2009: government decision concerning the pre-selection still pending. 2009-2010: geological surveys, consultations, territorial projects. B - High level and Intermediate level long lived waste (HL and IL-LL): Preparing disposal in a clay formation. 2012: public debate, 2013: site selection, 2015: application, 2025: start up. The Meuse Haute Marne Underground Research Laboratory Siting: the disposal facility (drilling campaigns), Construction of a Visitors' Centre designed to present the waste-repository project and its technological aspect. Inauguration scheduled in June 2009. 2 - Operated disposal facilities: A - Low and intermediate level short lived waste (LIL-SL) and Very low level waste (VLL). LIL-SL Manche Centre: 1969: start up, 1994: end of operation, 2003: institutional control period, Disposed volume (1969-1994): 527,000 m 3 , Impact of the facility ∼0,65 μSv/year (2008). Institutional control period monitoring: Radiological and chemical monitoring (Discharges, Underground water, Surface water), Capping system monitoring (Water-tightness performances, Rainfall water

Dry anaerobic digestion of the organic fraction of municipal solid waste

NARCIS (Netherlands)

Brummeler, ten E.

1993-01-01

Anaerobic digestion is an attractive technology for solid waste management. This thesis describes the technological potentials of dry anaerobic digestion of the organic fraction of Municipal Solid Waste (MSW) using batch systems. In 1985 a research programme was started to develop the so-

Different Methods for Conditioning Chloride Salt Wastes

International Nuclear Information System (INIS)

De Angelis, G.; Fedeli, C.; Capone, M.; Marzo, G.A.; Mariani, M.; Da Ros, M.; Giacobbo, F.; Macerata, E.; Giola, M.

2015-01-01

Three different methods have been used to condition chloride salt wastes coming from pyro-processes. Two of them allow to synthesise sodalite, a naturally occurring mineral containing chlorine: the former, starting from Zeolite 4A, which transforms the zeolite into sodalite; the latter, which starts from kaolinite, giving sodalite as well. In addition, a new matrix, termed SAP (SiO 2 -Al 2 O 3 -P 2 O 5 ), has been synthesised. It is able to form different mineral phases which occlude fission metals. The products from the different processes have been fully characterised. In particular the chemical durability of the final waste forms has been determined using the standard product consistency test. According to the results obtained, SAP seems to be a promising matrix for the incorporation of chloride salt wastes from pyro-processes. Financial support from the Nuclear Fission Safety Programme of the European Union (projects ACSEPT, contract FP7-CP-2007- 211 267, and SACSESS, Collaborative Project 323282), as well as from Italian Ministry for Economic Development (Accordo di Programma: Piano Annuale di Realizzazione 2008-2009) is gratefully acknowledged. (authors)

Disposal of radioactive wastes by UK NIREX Ltd

International Nuclear Information System (INIS)

Ginniff, M.E.

1989-01-01

In the United Kingdom UK Nirex Ltd., provides a comprehensive, long-term radioactive waste disposal service for low and intermediate level solid radioactive wastes arising from all radioactive operations in the country. The high level wastes which are not the responsibility of Nirex, are to be vitrified and stored for some 50 years. The low and intermediate wastes are to be emplaced in a deep underground repository and the developments during 1988 towards this objective are presented. Following the publication of a widely circulated consultation document entitled 'The Way Forward', design studies and site selection exercises for a deep underground repository were started. (author)

Pyrolysis Of Saudi Arabian Date Palm Waste: A Viable Option For Converting Waste Into Wealth

KAUST Repository

Hussain, Ahmad

2014-11-01

Saudi Arabia has about 23 million palm trees and it is the second largest producer of dates. The biomass from the trimmed branches of palm trees amount to more than 200,000 tons/year. This biomass waste can be used to produce many commercial products. There are several relevant technologies for conversion of biomass and solid wastes into higher value products. The starting point of the project is the pretreatment of palm solid wastes. Thermogravimetric analysis has been done to understand the pyrolysis behavior of palm date wastes. A fluidized bed (FB) has been designed and to study hydrodynamics and develop optimum conditions for the pyrolysis of palm wastes. A novel fluidized bed test rig has been designed and fabricated to carry out the pyrolysis of palm wastes. The pyrolysis is used to produce activated carbon and the waste can also be readily converted to liquid phenolic products. Liquid products are particularly interesting because they have a higher energy density and can be used to produce adhesives as well as biofuels for use in power generation and transport sector. Experimental results have indicated potential opportunities of using the date biomass waste as a potential fuel in the Kingdom of Saudi Arabia.

Radioactive wastes management development in Chile

International Nuclear Information System (INIS)

Mir, S.A.; Cruz, P.F.; Rivera, J.D.; Jorquera, O.H.

1994-01-01

A Facility for immobilizing and conditioning of radioactive wastes generated in Chile, has recently started in operation. It is a Radioactive Wastes Treatment Plant, RWTP, whose owner is Comision Chilena de Energia Nuclear, CCHEN. A Storgement Building of Conditioned Wastes accomplishes the facility for medium and low level activity wastes. The Project has been carried with participation of chilean professionals at CCHEN and Technical Assistance of International Atomic Energy Agency, IAEA. Processes developed are volume reduction by compaction; immobilization by cementation and conditioning. Equipment has been selected to process radioactive wastes into a 200 liters drum, in which wastes are definitively conditioned, avoiding exposition and contamination risks. The Plant has capacity to treat low and medium activity radioactive wastes produced in Chile due to Reactor Experimental No. 1 operation, and annex Laboratories in Nuclear Research Centers, as also those produced by users of nuclear techniques in Industries, Hospitals, Research Centers and Universities, in the whole country. With the infrastructure developed in Chile, a centralization of Radioactive Wastes Management activities is achieved. A data base system helps to control and register radioactive wastes arising in Chile. Generation of radioactive wastes in Chile, has found solution for the present production and that of near future

Greenhouse gas accounting and waste management

DEFF Research Database (Denmark)

Gentil, Emmanuel; Christensen, Thomas Højlund; Aoustin, E.

2009-01-01

Accounting of emissions of greenhouse gas (GHG) is a major focus within waste management. This paper analyses and compares the four main types of GHG accounting in waste management including their special features and approaches: the national accounting, with reference to the Intergovernmental...... specifically, the clean development mechanism (CDM) methodology, introduced to support cost-effective reduction in GHG emissions. These types of GHG accounting, in principle, have a common starting point in technical data on GHG emissions from specific waste technologies and plants, but the limited...... Panel on Climate Change (IPCC), the corporate level, as part of the annual reporting on environmental issues and social responsibility, life-cycle assessment (LCA), as an environmental basis for assessing waste management systems and technologies, and finally, the carbon trading methodology, and more...

Ethical aspects on Nuclear Waste

International Nuclear Information System (INIS)

Persson, Lars

1989-01-01

In an ethical assessment of how we shall deal with nuclear waste, one of the chief questions that arises is how to initiate action while at the same time taking into consideration uncertainties which are unavoidable seen from a long-term perspective. By means of different formulation and by proceeding from various starting-points, a two edged objective is established vis-a-vis repository facilities: safety in operation combined with reparability, with controls not necessary, but not impossible. Prerequisites for the realization of this objective are the continued advancement of knowledge and refinement of the qualifications required to deal with nuclear waste. The ethical considerations above could be the bases for the future legislation in the field of nuclear energy waste. (author)

Radioactive waste management in France

International Nuclear Information System (INIS)

Faussat, A.

1988-01-01

Solutions for radioactive waste management are already in existence and applied on an industrial scale for short-lived wastes. France has acquired an aknowledged expertise on the international level and several foreign contemporaries are interested in the relevant techniques developed. An intensive international cooperation has allowed to define bases for an underground deep repository for long-lived wastes. It is therefore important to choose a site which meets the expected storage conditions. This development work has been started in several countries in a similar way and which should be completed by the beginning of the next century. An 'open channel' with the public about this emotional topic can smooth the way for solutions by which mankind can master its technological challenges

A plan for Soviet nuclear waste

International Nuclear Information System (INIS)

Stone, R.

1992-01-01

If environmentalist forces are successful, the Russian government may soon establish the country's first comprehensive program for dealing with nuclear waste. Later this month the Russian parliament, back from its summer recess, is expected to begin considering a bill on this topic. A draft copy indicates that Russia is starting with the basics: It orders the government to develop a means of insulting waste from the environment, to form a national waste processing program, and to create a registry for tracking where spent atomic fuel is stored or buried. The bill comes on the heels of a November 1991 decree by Russian President Boris Yeltsin to step up efforts to deal with nuclear waste issues and to create a government registry of nuclear waste disposal sites by 1 January 1993. The former Soviet Union has come under fire from environmentalists for dumping low- and intermediate-level nuclear wastes in the Arctic Ocean and for improperly storing waste at sites in the southern Urals and Belarus. Adding to the bill's urgency is the fact that Russia is considering sites for underground repositories for high-level waste at Tomsk, Krasnoyarsk, Chelyabinsk, and on the Kola Peninsula

Start time delays in operating room: Different perspectives

Directory of Open Access Journals (Sweden)

Babita Gupta

2011-01-01

Full Text Available Background: Healthcare expenditure is a serious concern, with escalating costs failing to meet the expectations of quality care. The treatment capacities are limited in a hospital setting and the operating rooms (ORs. Their optimal utilization is vital in efficient hospital management. Starting late means considerable wait time for staff, patients and waste of resources. We planned an audit to assess different perspectives of the residents in surgical specialities and anesthesia and OR staff nurses so as to know the causative factors of operative delay. This can help develop a practical model to decrease start time delays in operating room (ORs. Aims: An audit to assess different perspectives of the Operating room (OR staff with respect to the varied causative factors of operative delay in the OR. To aid in the development of a practical model to decrease start time delays in ORs and facilitate on-time starts at Jai Prakash Narayan Apex Trauma centre (JPNATC, All India Institute of Medical Sciences (AIIMS, New Delhi. Methods: We prepared a questionnaire seeking the five main reasons of delay as per their perspective. Results: The available data was analysed. Analysis of the data demonstrated the common causative factors in start time operative delays as: a lack of proper planning, deficiencies in team work, communication gap and limited availability of trained supporting staff. Conclusions: The preparation of the equipment and required material for the OR cases must be done well in advance. Utilization of newer technology enables timely booking and scheduling of cases. Improved inter-departmental coordination and compliance with preanesthetic instructions needs to be ensured. It is essential that the anesthesiologists perform their work promptly, well in time . and supervise the proceedings as the OR manager. This audit is a step forward in defining the need of effective OR planning for continuous quality improvement.

Startup of the remote laboratory-scale waste-treatment facility

International Nuclear Information System (INIS)

Knox, C.A.; Siemens, D.H.; Berger, D.N.

1981-01-01

The Remote Laboratory-Scale Waste-Treatment Facility was designed as a system to solidify small volumes of radioactive liquid wastes. The objectives in operating this facility are to evaluate solidification processes, determine the effluents generated, test methods for decontaminating the effluents, and provide radioactive solidified waste products for evaluation. The facility consists of a feed-preparation module, a waste-solidification module and an effluent-treatment module. The system was designed for remote installation and operation. Several special features for remotely handling radioactive materials were incorporated into the design. The equipment was initially assembled outside of a radiochemical cell to size and fabricate the connecting jumpers between the modules and to complete some preliminary design-verification tests. The equipment was then disassembled and installed in the radiochemical cell. When installation was completed the entire system was checked out with water and then with a nonradioactive simulated waste solution. The purpose of these operations was to start up the facility, find and solve operational problems, verify operating procedures and train personnel. The major problems experienced during these nonradioactive runs were plugging of the spray calciner nozzle and feed tank pumping failures. When these problems were solved, radioactive operations were started. This report describes the installation of this facility, its special remote design feature and the startup operations

MIIT: International in-situ testing of nuclear-waste glasses: Performance of SRS simulated waste glass after five years of burial at the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Wicks, G.G.; Lodding, A.R.; Macedo, P.B.; Clark, D.E.

1991-01-01

In July of 1986, the first in-situ test involving burial of simulated high-level waste (HLW) forms conducted in the United States was started. This program, called the Materials Interface Interactions Test or MIIT, comprises the largest, most cooperative field-testing venture in the international waste management community. In July of 1991, the experimental portion of the 5-year MIIT study was completed on schedule. During this time interval, many in-situ measurements were performed, thousands of brine analyses conducted, and hundreds of waste glass and package components exhumed and evaluated after 6 mo., 1 yr., 2 yr. and 5 yr. burial periods. Although analyses are still in progress, the performance of SRS waste glass based on all data currently available has been seen to be excellent thus far. Initial analyses and assessment of Savannah River (SR) waste glass after burial in WIPP at 90 degrees C for 5 years are presented in this document

Quantity assessment of waste in the dismantlement of liquid waste treatment plant and its actual state

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.)

Emissions from US waste collection vehicles

International Nuclear Information System (INIS)

Maimoun, Mousa A.; Reinhart, Debra R.; Gammoh, Fatina T.; McCauley Bush, Pamela

2013-01-01

Highlights: ► Life-cycle emissions for alternative fuel technologies. ► Fuel consumption of alternative fuels for waste collection vehicles. ► Actual driving cycle of waste collection vehicles. ► Diesel-fueled waste collection vehicle emissions. - Abstract: This research is an in-depth environmental analysis of potential alternative fuel technologies for waste collection vehicles. Life-cycle emissions, cost, fuel and energy consumption were evaluated for a wide range of fossil and bio-fuel technologies. Emission factors were calculated for a typical waste collection driving cycle as well as constant speed. In brief, natural gas waste collection vehicles (compressed and liquid) fueled with North-American natural gas had 6–10% higher well-to-wheel (WTW) greenhouse gas (GHG) emissions relative to diesel-fueled vehicles; however the pump-to-wheel (PTW) GHG emissions of natural gas waste collection vehicles averaged 6% less than diesel-fueled vehicles. Landfill gas had about 80% lower WTW GHG emissions relative to diesel. Biodiesel waste collection vehicles had between 12% and 75% lower WTW GHG emissions relative to diesel depending on the fuel source and the blend. In 2011, natural gas waste collection vehicles had the lowest fuel cost per collection vehicle kilometer travel. Finally, the actual driving cycle of waste collection vehicles consists of repetitive stops and starts during waste collection; this generates more emissions than constant speed driving

Shippingport Station Decommissioning Project Start of Physical Decommissioning

International Nuclear Information System (INIS)

Crimi, F. P.

1987-01-01

The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy, and the turbine-generator and balance of plant, which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by DOE from Duquesne Light Company. The Shippingport Station Decommissioning Project is being performed under contract to the DOE by the General Electric Company and its integrated subcontractor, Morrison-Knudsen Company. as the Decommissioning Operations Contractor. This paper describes the current status of the physical decommissioning work, which started September 1985. The preparations required to start a major decommissioning work effort in a safe and cost effective manner are discussed including the development and implementation of a cost/schedule control system. The detailed plan required to ensure that people, property, and procedures are ready in sufficient time to support the start of physical decommissioning is also discussed. The total estimated cost of the Shippingport Station Decommissioning Project should be $98.3 M, with the Project scheduled for completion in April 1990. As the decommissioning of the first commercial-scale nuclear power plant, the Shippingport Project is expected to set the standard for safe, cost-effective demolition of nuclear plants

Hanford Tank Waste Treatment and Immobilization Plant (WTP) Waste Feed Qualification Program Development Approach - 13114

Energy Technology Data Exchange (ETDEWEB)

Markillie, Jeffrey R.; Arakali, Aruna V.; Benson, Peter A.; Halverson, Thomas G. [Hanford Tank Waste Treatment and Immobilization Plant Project, Richland, WA 99354 (United States); Adamson, Duane J.; Herman, Connie C.; Peeler, David K. [Savannah River National Laboratory, Aiken, SC 29808 (United States)

2013-07-01

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is a nuclear waste treatment facility being designed and constructed for the U.S. Department of Energy by Bechtel National, Inc. and subcontractor URS Corporation (under contract DE-AC27-01RV14136 [1]) to process and vitrify radioactive waste that is currently stored in underground tanks at the Hanford Site. A wide range of planning is in progress to prepare for safe start-up, commissioning, and operation. The waste feed qualification program is being developed to protect the WTP design, safety basis, and technical basis by assuring acceptance requirements can be met before the transfer of waste. The WTP Project has partnered with Savannah River National Laboratory to develop the waste feed qualification program. The results of waste feed qualification activities will be implemented using a batch processing methodology, and will establish an acceptable range of operator controllable parameters needed to treat the staged waste. Waste feed qualification program development is being implemented in three separate phases. Phase 1 required identification of analytical methods and gaps. This activity has been completed, and provides the foundation for a technically defensible approach for waste feed qualification. Phase 2 of the program development is in progress. The activities in this phase include the closure of analytical methodology gaps identified during Phase 1, design and fabrication of laboratory-scale test apparatus, and determination of the waste feed qualification sample volume. Phase 3 will demonstrate waste feed qualification testing in support of Cold Commissioning. (authors)

Occurrence of refeeding syndrome in adults started on artificial nutrition support: prospective cohort study.

Science.gov (United States)

Rio, Alan; Whelan, Kevin; Goff, Louise; Reidlinger, Dianne Patricia; Smeeton, Nigel

2013-01-11

Refeeding syndrome is a potentially life-threatening condition characterised by severe intracellular electrolyte shifts, acute circulatory fluid overload and organ failure. The initial symptoms are non-specific but early clinical features are severely low-serum electrolyte concentrations of potassium, phosphate or magnesium. Risk factors for the syndrome include starvation, chronic alcoholism, anorexia nervosa and surgical interventions that require lengthy periods of fasting. The causes of the refeeding syndrome are excess or unbalanced enteral, parenteral or oral nutritional intake. Prevention of the syndrome includes identification of individuals at risk, controlled hypocaloric nutritional intake and supplementary electrolyte replacement. To determine the occurrence of refeeding syndrome in adults commenced on artificial nutrition support. Prospective cohort study. Large, single site university teaching hospital. Recruitment period 2007-2009. 243 adults started on artificial nutrition support for the first time during that admission recruited from wards and intensive care. occurrence of the refeeding syndrome. Secondary outcome: analysis of the risk factors which predict the refeeding syndrome. Tertiary outcome: mortality due to refeeding syndrome and all-cause mortality. 133 participants had one or more of the following risk factors: body mass index 15% in the preceding 3-6 months, very little or no nutritional intake >10 days, history of alcohol or drug abuse and low baseline levels of serum potassium, phosphate or magnesium prior to recruitment. Poor nutritional intake for more than 10 days, weight loss >15% prior to recruitment and low-serum magnesium level at baseline predicted the refeeding syndrome with a sensitivity of 66.7%: specificity was >80% apart from weight loss of >15% which was 59.1%. Baseline low-serum magnesium was an independent predictor of the refeeding syndrome (p=0.021). Three participants (2% 3/243) developed severe electrolyte shifts

Is a Finnish municipality going to accept the radioactive wastes

International Nuclear Information System (INIS)

Harmaajaervi, I.

1997-01-01

The article reviews the methods and results of the questionnaire study collecting information on the public attitudes with regard to radioactive waste disposal in Finland. The study started in December 1996 and concentrated on the population living in the areas of radioactive waste disposal site investigations, Eurajoki, Aeaenekoski and Kuhmo. The items of the questionnaire asked about the impacts of the radioactive waste disposal on the environment, and also on public health and general safety. The results addressed the importance of the relevant and comprehensive information of the radioactive waste management to the public. The study is a part of the Publicly administrated nuclear waste management programme (JYT2) in Finland

Recycling by coverting organic waste to fertilize at Ikata Nuclear Power Station

International Nuclear Information System (INIS)

Kubota, T.; Matsuoka, H.

2008-01-01

In order to cope with global- warming and Dioxin issue, we started the Project in which all kinds of organic wastes originated on site are fermented to organic fertilizer with the help of YM bacteria in 2001. And in 2006 our product was officially approved as fertilizer by regulatory body, and then we started to sell these fertilizers to farmers near-by. Among many power stations in Japan, Ikata Nuclear Power Station may be the first plant where organic wastes are totally reused as commercial-based fertilizer. (author)

DWPF waste form compliance plan (Draft Revision)

International Nuclear Information System (INIS)

Plodinec, M.J.; Marra, S.L.

1991-01-01

The Department of Energy currently has over 100 million liters of high-level radioactive waste in storage at the Savannah River Site (SRS). In the late 1970's, the Department of Energy recognized that there were significant safety and cost advantages associated with immobilizing the high-level waste in a stable solid form. Several alternative waste forms were evaluated in terms of product quality and reliability of fabrication. This evaluation led to a decision to build the Defense Waste Processing Facility (DWPF) at SRS to convert the easily dispersed liquid waste to borosilicate glass. In accordance with the NEPA (National Environmental Policy Act) process, an Environmental Impact Statement was prepared for the facility, as well as an Environmental Assessment of the alternative waste forms, and issuance of a Record of Decision (in December, 1982) on the waste form. The Department of Energy, recognizing that start-up of the DWPF would considerably precede licensing of a repository, instituted a Waste Acceptance Process to ensure that these canistered waste forms would be acceptable for eventual disposal at a federal repository. This report is a revision of the DWPF compliance plan

Wasting and stunting – similarities and differences; policy and programmatic implications

International Nuclear Information System (INIS)

Briend, André; Khara, Tanya; Dolan, Carmel

2014-01-01

Full text: The terms wasting and stunting were introduced by Waterlow to differentiate among underweight children those with a low weight-for-height (wasted) from those with a low height-for-age (stunted). Wasting is often called acute malnutrition and stunting chronic malnutrition but these terms may be misleading, and may just reflect that it takes a longer time to diagnose linear growth retardation. These two forms of malnutrition are associated with changes in body composition with a reduced muscle mass but usually a normal brain size in relation to body weight. These changes are more pronounced but more easily corrected in wasting. The reduced muscle mass present in stunting may persist into adult life and may be associated with an increased fat mass. Muscle is the main store of amino-acids and other essential nutrients needed for the body’s immune response and is a major determinant of survival in infections. The low muscle mass observed in both stunting and wasting is likely to explain the association between these two conditions and increased mortality. Hence, health and nutrition programmes aiming to reduce mortality need to prevent both wasting and stunting, especially in young children who have a low muscle ass to start with. Children having an insufficient food intake lose weight and become wasted but also stop growing in height, becoming stunted if untreated. Growth in height resumes only after wasting has been at least partially corrected. Hence detecting and treating wasting in a timely fashion also helps to prevent stunting. The recent discovery that bone and body fat are both endocrine organs interacting with each other and that bone regulates energy metabolism through osteocalcin (a hormone produced by bone) may explain these observations. Stunting can also occur in the absence of wasting. A possible explanation is that linear growth requires synthesis of cartilage and bone tissues, which contain more phosphorus, calcium, magnesium and sulphur

Characteristics of fuel cycle waste

International Nuclear Information System (INIS)

Aquilina, C.A.; Everette, S.E.

1982-01-01

The Low-Level Waste Management System started in 1979 to describe and model the existing commercial low-level waste management system. The system description produced is based on the identification of the different elements making up both the fuel and non-fuel cycle and their relationships to each other. A systems model based on the system description can accurately reflect the flow of low-level waste from generator to disposal site and is only limited by the reliability of the information it uses. For both the fuel cycle and non-fuel cycle large quantities of information is required in order to allow the system to operate at its full potential. Work is ongoing to collect this information. Significant progress is being made in the fuel cycle area primarily because the majority of fuel cycle low-level radioactive waste is produced by commercial power reactor plant operations. The Low-Level Waste Management system is only beginning to derive the benefits to be obtained from an accurate low-level waste management information system. As data is verified and analyzed, results on a national as well as individual organization level will be gained. Comparisons to previous studies will be made. Accurate projections of waste volumes and activities to be produced, projected impacts of waste streams of treatment or management changes are only examples of information to be produced. 1 figure, 1 table

POSSIBLE METHODS FOR PREVENTING PLASTIC WASTE FROM ENTERING THE MARINE ENVIRONMENT

OpenAIRE

David, Minodora-Florentina; Burdukovska, Valentina; Heng, Chen

2013-01-01

The widespread use of plastic has become a huge threat for the marine environment. With problems such as the oceanic garbage patches increasing more and more in scale, the focus is set on how could plastic waste be prevented from entering the oceans and adversely affecting the wildlife. Since the largest accumulation of plastic waste is found in the North Pacific Gyre, we have looked at the surrounding countries with the highest waste generation. By using the pyramid of waste as a starting po...

Waste Vitrification Projects Throughout the US Initiated by SRS

International Nuclear Information System (INIS)

Jantzen, C.M.; Whitehouse, J.C.; Smith, M.E.; Pickett, J.B.; Peeler, D.K.

1998-05-01

Technologies are being developed by the U. S. Department of Energy's (DOE) Nuclear Facility sites to convert high-level, low-level, and mixed wastes to a solid stabilized waste form for permanent disposal. Vitrification is one of the most important and environmentally safest technologies being developed. The Environmental Protection Agency (EPA) has declared vitrification the best demonstrated available technology for high-level radioactive waste and produced a Handbook of Vitrification Technologies for Treatment of Hazardous and Radioactive Waste. The Defense Waste Processing Facility being tested at will soon start vitrifying the high-level waste at. The DOE Office of Technology Development has taken the position that mixed waste needs to be stabilized to the highest level reasonably possible to ensure that the resulting waste forms will meet both current and future regulatory specifications. Vitrification produces durable waste forms at volume reductions up to 97%. Large reductions in volume minimize long-term storage costs making vitrification cost effective on a life cycle basis

Quick-start of full-scale anaerobic digestion (AD) using aeration

Energy Technology Data Exchange (ETDEWEB)

Lagerkvist, Anders, E-mail: al@ltu.se; Pelkonen, Markku; Wikström, Tommy

2015-04-15

Highlights: • A fast, and original, start up procedure for anaerobic digestors has been applied at full scale. • The development of a methanogenic culture has been documented using fluorescent in situ hybridization. • The technique can be widely applied. - Abstract: A conventional 1300 m{sup 3} continuously stirred anaerobic tank reactor at the city of Boden, north Sweden, which was receiving a feed of both sewage sludge and food waste, was put out of operation due to the build-up of a float phase. The reactor was emptied and cleaned. At start-up there was no methanogenic sludge available, so an unconventional start-up procedure was applied: The reactor was rapidly (8 days with 1200 kg of total solids (TS) added daily) filled with thickened, and slightly acidic sewage sludge, showing only slight methane generation, which was subsequently heated to 55 °C. Then compressed air was blown into the digester and within a month a fully functional methanogenic culture was established. The transfer from acidogenic to methanogenic conditions happened in about one week. As a start-up technique this is fast and cost efficient, it only requires the access of a compressor, electricity and a source of air. In total, about 16 tonnes of oxygen were used. It is proposed that this method may also be used as an operational amendment technique, should a reactor tend to acidify.

Quick-start of full-scale anaerobic digestion (AD) using aeration

International Nuclear Information System (INIS)

Lagerkvist, Anders; Pelkonen, Markku; Wikström, Tommy

2015-01-01

Highlights: • A fast, and original, start up procedure for anaerobic digestors has been applied at full scale. • The development of a methanogenic culture has been documented using fluorescent in situ hybridization. • The technique can be widely applied. - Abstract: A conventional 1300 m 3 continuously stirred anaerobic tank reactor at the city of Boden, north Sweden, which was receiving a feed of both sewage sludge and food waste, was put out of operation due to the build-up of a float phase. The reactor was emptied and cleaned. At start-up there was no methanogenic sludge available, so an unconventional start-up procedure was applied: The reactor was rapidly (8 days with 1200 kg of total solids (TS) added daily) filled with thickened, and slightly acidic sewage sludge, showing only slight methane generation, which was subsequently heated to 55 °C. Then compressed air was blown into the digester and within a month a fully functional methanogenic culture was established. The transfer from acidogenic to methanogenic conditions happened in about one week. As a start-up technique this is fast and cost efficient, it only requires the access of a compressor, electricity and a source of air. In total, about 16 tonnes of oxygen were used. It is proposed that this method may also be used as an operational amendment technique, should a reactor tend to acidify

Financing waste to energy plants

International Nuclear Information System (INIS)

Woodward, A.

1991-01-01

Waste-to-energy projects are going ahead in the U.K., they are being project financed and they will make a valuable contribution to environmentally acceptable waste disposal and clean energy within the U.K. Starting from the premise that project sponsors must compete for funds therefore behoves the project sponsor to adapt his proposal to the needs of the investor rather than the other way around. Some of the major potential suppliers of funds are briefly surveyed. It is concluded that waste-to-energy projects do not fit easily into the business plans of venture capital companies, pension funds and banks. Projects must be reworked so that a more favourable opportunity can be offered to potential funders. Ways of achieving this through improved economics and reductions in risk and uncertainty are examined. (author)

Considerations for Informed Pursuit of Zero Waste: Lessons from Two Case Studies

OpenAIRE

Thangavelu, Jennifer Anne

2013-01-01

Starting in the early 2000s, a number of U.S. communities have adopted "zero waste" commitments to reduce waste as much as possible through recycling, composting, and other means. Little in-depth information exists about the impetus for or efficacy of these efforts. The author sought to build knowledge on the topic by conducting case studies of two communities: the zero waste efforts of Boulder, Colorado, and the Zero Waste Zones established in Atlanta. The two cases presented an interesting ...

Radioactive waste incineration system cold demonstration test

Energy Technology Data Exchange (ETDEWEB)

Hozumi, Masahiro; Takaoku, Yoshinobu; Koyama, Shigeru; Nagae, Madoka; Seike, Yasuhiko; Yamanaka, Yasuhiro; Shibata, Kenji; Manabe, Kyoichi

1984-12-01

To demonstrate Waste Incineration System (WIS) which our company has been licensed by Combustion Engineering Inc., USA we installed a demonstration test plant in our Hiratsuka Research Laboratory and started the demonstration test on January 1984. One of the characteristics of this system is to be able to process many kinds of wastes with only one system, and to get high volume reduction factors. In our test plant, we processed paper, cloth, wood, polyethylene sheets as the samples of solid combustible wastes and spent ion exchange resins with incineration and processed condensed liquid wastes with spray drying. We have got good performances and enough Decontamination Factor (DF) data for the dust control equipment. In this paper, we introduce this demonstration test plant and report the test results up to date. (author).

Low- and intermediate-level waste management practices in Japan

International Nuclear Information System (INIS)

Tsuchiya, M.

1982-01-01

At present, disposal of low-level radioactive wastes is yet to be carried out in Japan. Liquid wastes, except for the diluted discharge of very low-level waste into the environment, are mostly solidified with cement or bitumen to be packed in 200 litre drums and put in storage. Solid wastes, on the other hand, are mostly put into in 200 litre drums, some of them being incinerated beforehand. Efforts are being made to develop technology for reducing the production of wastes. Regarding sea disposal, a test dumping program has been forestalled by the opposition of South Pacific islanders, but we are endeavoring to promote their understandings on this matter. Regarding land disposal, first we are going to start centralized storage, then shift to underground disposal

Safety Evaluation for Hull Waste Treatment Process in JNC

International Nuclear Information System (INIS)

Kojima, H.; Kurakata, K.

2002-01-01

Hull wastes and some scrapped equipment are typical radioactive wastes generated from reprocessing process in Tokai Reprocessing Plant (TRP). Because hulls are the wastes remained in the fuel shearing and dissolution, they contain high radioactivity. Japan Nuclear Cycle Development Institute (JNC) has started the project of Hull Waste Treatment Facility (HWTF) to treat these solid wastes using compaction and incineration methods since 1993. It is said that Zircaloy fines generated from compaction process might burn and explode intensely. Therefore explosive conditions of the fines generated in compaction process were measured. As these results, it was concluded that the fines generated from the compaction process were not hazardous material. This paper describes the outline of the treatment process of hulls and results of safety evaluation

Investigation of Starting Romantic Intimacy in Emerging Adulthood in Terms of Self-Esteem, Gender and Gender Roles

Science.gov (United States)

Eryilmaz, Ali; Atak, Hasan

2011-01-01

This study aims, firstly, to examine whether gender plays a decisive role in starting romantic intimacy during the emerging adulthood period; secondly, to compare emerging adults who are assigned different gender roles, in terms of starting romantic intimacy; and thirdly, to analyze the level at which self-esteem and gender roles predict the…

A Comparison of Developmental Sentence Scores from Head Start Children Collected in Four Conditions

Science.gov (United States)

Longhurst, Thomas M.; File, Judy J.

1977-01-01

In a comparison of expressive language in different settings, 20 economically disadvantaged students in a Head Start program were divided into four groups: single-object picture, toy, multi-object picture, and adult-child conversation. (CL)

An approach for the reasonable TRU waste management in NUCEF

International Nuclear Information System (INIS)

Mineo, H.; Dojiri, S.; Takeshita, I.; Tsujino, T.; Matsumura, T.; Nishizawa, I.; Sugikawa, S.

1995-01-01

The Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) has started its hot operation at the beginning of 1995, where TRU (transuranic) elements are used. The management of TRU waste arisen in the facility is very important issue. Liquid and solid wastes containing TRU elements are generated mainly from the Fuel Treatment System for critical experiments and from the researches of reprocessing process and TRU waste management for reprocessing plants using hot cells and glove-boxes. The TRU waste management in NUCEF is based on the classification of waste, and is to maximize the recycle of reagents and the reuse of TRU elements separated from the waste, as well as to reduce the waste volume and to lower the risk of waste by advanced separation and solidification. In the future, the separation and solidification of TRU elements in the tanks of liquid waste, and the classification and discrimination of solid wastes, will be carried out applying the outcomes of the development by the researches in NUCEF. (authors)

Technology Roadmapping for Waste Management

International Nuclear Information System (INIS)

Bray, O.

2003-01-01

Technology roadmapping can be an effective strategic technology planning tool. This paper describes a process for customizing a generic technology roadmapping process. Starting with a generic process reduces the learning curve and speeds up the roadmap development. Similarly, starting with a generic domain model provides leverage across multiple applications or situations within the domain. A process that combines these two approaches facilitates identifying technology gaps and determining common core technologies that can be reused for multiple applications or situations within the domain. This paper describes both of these processes and how they can be integrated. A core team and a number of technology working groups develop the technology roadmap, which includes critical system requirements and targets, technology areas and metrics for each area, and identifies and evaluates possible technology alternatives to recommend the most appropriate ones to pursue. A generalized waste management model, generated by considering multiple situations or applications in terms of a generic waste management model, provides the domain requirements for the technology roadmapping process. Finally, the paper discusses lessons learns from a number of roadmapping projects

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)

Project report for the commercial disposal of mixed low-level waste debris

Energy Technology Data Exchange (ETDEWEB)

Andrews, G.; Balls, V.; Shea, T.; Thiesen, T.

1994-05-01

This report summarizes the basis for the commercial disposal of Idaho National Engineering Laboratory (INEL) mixed low-level waste (MLLW) debris and the associated activities. Mixed waste is radioactive waste plus hazardous waste as defined by the Resource Conservation and Recovery Act (RCRA). The critical factors for this project were DOE 5820.2A exemption, contracting mechanism, NEPA documentation, sampling and analysis, time limitation and transportation of waste. This report also will provide a guide or a starting place for future use of Envirocare of Utah or other private sector disposal/treatment facilities, and the lessons learned during this project.

Project report for the commercial disposal of mixed low-level waste debris

International Nuclear Information System (INIS)

Andrews, G.; Balls, V.; Shea, T.; Thiesen, T.

1994-05-01

This report summarizes the basis for the commercial disposal of Idaho National Engineering Laboratory (INEL) mixed low-level waste (MLLW) debris and the associated activities. Mixed waste is radioactive waste plus hazardous waste as defined by the Resource Conservation and Recovery Act (RCRA). The critical factors for this project were DOE 5820.2A exemption, contracting mechanism, NEPA documentation, sampling and analysis, time limitation and transportation of waste. This report also will provide a guide or a starting place for future use of Envirocare of Utah or other private sector disposal/treatment facilities, and the lessons learned during this project

Nuclear wastes and public trust

International Nuclear Information System (INIS)

Flynn, J.; Slovic, P.

1993-01-01

Citing public fear and mistrust, strong opposition to the proposed Yucca Mountain repository site, and less-than-exemplary performance by the Department of Energy (DOE), two private researchers believe present high-level radioactive waste-disposal plans may have to be scrapped. Government and the nuclear industry may have to start over. Policy makers should seek to develop new relationships with communities and states where suitable disposal sites exist. These relationships may require that citizen groups and local institutions be given unprecedented authority in locating and operating such facilities. Contrary to popular impressions, there is still time to take a new approach. The US Nuclear Regulatory Commission says present on-site storage arrangements offer a safe alternative for 100 years or more. The sense of immediate crisis and cries for immediate solutions should be calmed and a more considered strategy brought to the public debate. For starters, the researchers propose that the problems of defense waste be separated from the problems of commercial waste. They also suggest that DOE be assigned responsibility for defense waste and a new agency be created to handle high-level commercial waste

Method of solidifying radioactive waste by plastics

International Nuclear Information System (INIS)

Yasumura, Keijiro; Tomita, Toshihide.

1976-01-01

Purpose: To prevent leakage of radioactivity by providing corrosion-resistant layer on the inner surface of a waste container for radioactive waste. Constitution: The inner periphery and bottom of a drum can is lined with an non-flammable cloth of such material as asbestos. This drum is filled with a radioactive waste in the form of powder or pellets. Then, a mixture of a liquid plastic monomer and a polymerization starting agent is poured at a normal temperature, and the surface is covered with a non-flammable cloth. The plastic monomer and radioactive waste are permitted to impregnate the non-flammable cloth and are solidified there. Thus, even if the drum can is corroded at the sea bottom after disposal it in the ocean, it is possible to prevent the waste from permeating into the outer sea water because of the presence of the plastic layer on the inside. Styrene is used as the monomer. (Aizawa, K.)

Guide Of Treatment On Noxious Waste Of Experiment

Energy Technology Data Exchange (ETDEWEB)

NONE

1987-05-15

This book deals with environmental safe management and smooth driving of facilities, which indicates purpose of this guide, responsibility of environmental safe management, division of collect of starting point treatment, batch processing system, treatment of noxious waste of experiment, regulation of harmful waste such as medicine, corrosivity liquid, and treatment of cleaning solution of chrome-sulfuric acid, and regulation of Kyungpook National University Department Environmental Engineering Research Center, environmental protection law and the other related law.

Guide Of Treatment On Noxious Waste Of Experiment

International Nuclear Information System (INIS)

1987-05-01

This book deals with environmental safe management and smooth driving of facilities, which indicates purpose of this guide, responsibility of environmental safe management, division of collect of starting point treatment, batch processing system, treatment of noxious waste of experiment, regulation of harmful waste such as medicine, corrosivity liquid, and treatment of cleaning solution of chrome-sulfuric acid, and regulation of Kyungpook National University Department Environmental Engineering Research Center, environmental protection law and the other related law.

Treatment of liquid radioactive waste: Evaporation

International Nuclear Information System (INIS)

Pfeiffer, R.

1982-01-01

About 10.000 m 3 of low active liquid waste (LLW) arise in the Nuclear Research Center Karlsruhe. Chemical contents of this liquid waste are generally not declared. Resulting from experiments carried out in the Center during the early sixties, the evaporator facility was built in 1968 for decontamination of LLW. The evaporators use vapor compression and concentrate recirculation in the evaporator sump by pumps. Since 1971 the medium active liquid waste (MLW) from the Karlsruhe Reprocessing Plant (WAK) was decontaminated in this evaporator facility, too. By this time the amount of low liquid waste (LLW) had been decontaminated without mentionable interruptions. Afterwards a lot of interruptions of operations occurred, mainly due to leakages of pumps, valves and pipes. There was also a very high radiation level for the operating personnel. As a consequence of this experience a new evaporator facility for decontamination of medium active liquid waste was built in 1974. This facility started operation in 1976. The evaporator has natural circulation and is heated by steam through a heat exchanger. (orig./RW)

CEA's waste management policy and strategy. Lessons learned - 59201

International Nuclear Information System (INIS)

Dall'ava, Didier

2012-01-01

Document available in abstract form only. Full text of publication follows: Radioactive wastes are generated during operation as well as during the decontamination and dismantling of CEA's nuclear facility/installation. The safe and responsible management of radioactive wastes at all stages is an essential requirement of the regulatory system. The management covers the whole sequence of operations starting with the generation of waste and ending with its disposal. The disposal here means discarding of waste with no intention for retrieval. It is important to note here that the safety principles and practices that are applicable during the operational phase are also applicable during the decommissioning phase. As the radioactive waste arising is an inevitable outcome of decommissioning work, all the regulatory requirements associated with decommissioning remain in force in waste management. This presentation deals initially with the regulatory standards related to the management of wastes. As the management of radioactive wastes inevitably includes treatment and conditioning of wastes, following treatment and conditioning of wastes, storage, transportation and eventual disposal are the logical outcome of the radioactive wastes, processes are at any time improved based on the feedback experience and the lessons learned. (author)

Stability of disposal rooms during waste retrieval

International Nuclear Information System (INIS)

Brandshaug, T.

1989-03-01

This report presents the results of a numerical analysis to determine the stability of waste disposal rooms for vertical and horizontal emplacement during the period of waste retrieval. It is assumed that waste retrieval starts 50 years after the initial emplacement of the waste, and that access to and retrieval of the waste containers take place through the disposal rooms. It is further assumed that the disposal rooms are not back-filled. Convective cooling of the disposal rooms in preparation for waste retrieval is included in the analysis. Conditions and parameters used were taken from the Nevada Nuclear Waste Storage Investigation (NNWSI) Project Site Characterization Plan Conceptual Design Report (MacDougall et al., 1987). Thermal results are presented which illustrate the heat transfer response of the rock adjacent to the disposal rooms. Mechanical results are presented which illustrate the predicted distribution of stress, joint slip, and room deformations for the period of time investigated. Under the assumption that the host rock can be classified as ''fair to good'' using the Geomechanics Classification System (Bieniawski, 1974), only light ground support would appear to be necessary for the disposal rooms to remain stable. 23 refs., 28 figs., 2 tabs

Rad-waste treatment

International Nuclear Information System (INIS)

1996-01-01

The spent fuel coming from Slovak NPPs have partially been transported to the former Soviet Union, and a part of it is stored in an interim spent fuel wet storage. In compliance with the worldwide practices, further medium-term possibilities of storing in dry storages are under preparation. Disposal of a spent fuel and other high-level active wastes in a deep geological formation repository is the final solution. At present, there are geological investigations of possible sites in progress in Slovakia. Mochovce repository is a factory for a final disposal of compacted low and intermediate level radioactive wastes coming from the Slovak NPPs. This is a near-surface facility of a construction similar to the one used for disposal of radioactive wastes in France, Spain, Japan, Czech Republic, U.S.A, etc. Quality of the design, construction and functioning of the Mochovce's repository was assessed by an international team of experts within a special IAEA programme (WATRP). Having familiarized with the final report of the IAEA mission, Nuclear Regulatory Authority of the Slovak Republic (NRA SR) issued its position early in 1995, in which NRA SR required additional adjustment of the repository itself. Based on the NRA SR's position, Mochovce NPP invited experts from a number of institutions in September 1995 to discuss the NRA SR's requirements. Following was recommended by the experts: (1) to perform a complementary engineering-geological investigation on the site, (2) to use geophysical methods to verify existence of geological faults. In the next part a radioactive wastes that were treated at radioactive waste treatment lines in 1995 are listed. In 1995, the Chief Inspector of NRA SR issued an instruction that radioactive waste department should start inspections of radioactive waste treatment right in hospitals, research institutes and industries. Therefore, a total of 14 such workplaces were incorporated into a plan of inspections in 1995

Buying less and wasting less food. Changes in household food energy purchases, energy intakes and energy density between 2007 and 2012 with and without adjustment for food waste.

Science.gov (United States)

Whybrow, Stephen; Horgan, Graham W; Macdiarmid, Jennie I

2017-05-01

Consumers in the UK responded to the rapid increases in food prices between 2007 and 2009 partly by reducing the amount of food energy bought. Household food and drink waste has also decreased since 2007. The present study explored the combined effects of reductions in food purchases and waste on estimated food energy intakes and dietary energy density. The amount of food energy purchased per adult equivalent was calculated from Kantar Worldpanel household food and drink purchase data for 2007 and 2012. Food energy intakes were estimated by adjusting purchase data for food and drink waste, using waste factors specific to the two years and scaled for household size. Scotland. Households in Scotland (n 2657 in 2007; n 2841 in 2012). The amount of food energy purchased decreased between 2007 and 2012, from 8·6 to 8·2 MJ/adult equivalent per d (Pfood waste, estimated food energy intake was not significantly different (7·3 and 7·2 MJ/adult equivalent per d for 2007 and 2012, respectively; P=0·186). Energy density of foods purchased increased slightly from 700 to 706 kJ/100 g (P=0·010). While consumers in Scotland reduced the amount of food energy that they purchased between 2007 and 2012, this was balanced by reductions in household food and drink waste over the same time, resulting in no significant change in net estimated energy intake of foods brought into the home.

Aube's very-low-level waste storage Center. Annual report 2008

International Nuclear Information System (INIS)

2008-01-01

After a presentation of the ANDRA (the French national Agency for radioactive waste management), its missions, its facilities, and its financing, this report reviews the activity of the very-low-activity level waste storage centre located in the boroughs of Morvilliers and La Chaise in the Aube district (France), the operation of which started in 2003. It briefly specifies the waste types and origins, its facilities, its operation data for 2008. It describes its safety, security, and radioprotection installations and actions, its environment monitoring activity, its actions for information transparency

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

Listed waste history at Hanford facility TSD units

International Nuclear Information System (INIS)

Miskho, A.G.

1996-01-01

This document was prepared to close out an occurrence report that Westinghouse Hanford Company issued on December 29, 1994. Occurrence Report RL-WHC-GENERAL-1994-0020 was issued because knowledge became available that could have impacted start up of a Hanford Site facility. The knowledge pertained to how certain wastes on the Hanford Site were treated, stored, or disposed of. This document consolidates the research performed by Westinghouse Hanford Company regarding listed waste management at onsite laboratories that transfer waste to the Double-Shell Tank System. Liquid and solid (non-liquid) dangerous wastes and mixed wastes at the Hanford Site are generated from various Site operations. These wastes may be sampled and characterized at onsite laboratories to meet waste management requirements. In some cases, the wastes that are generated in the field or in the laboratory from the analysis of samples require further management on the Hanford Site and are aggregated together in centralized tank storage facilities. The process knowledge presented herein documents the basis for designation and management of 242-A Evaporator Process Condensate, a waste stream derived from the treatment of the centralized tank storage facility waste (the Double-Shell Tank System). This document will not be updated as clean up of the Hanford Site progresses

Waste-to-Chemicals for a Circular Economy: The Case of Urea Production (Waste-to-Urea).

Science.gov (United States)

Antonetti, Elena; Iaquaniello, Gaetano; Salladini, Annarita; Spadaccini, Luca; Perathoner, Siglinda; Centi, Gabriele

2017-03-09

The economics and environmental impact of a new technology for the production of urea from municipal solid waste, particularly the residue-derived fuel (RdF) fraction, is analyzed. Estimates indicate a cost of production of approximately €135 per ton of urea (internal rate of return more than 10 %) and savings of approximately 0.113 tons of CH 4 and approximately 0.78 tons of CO 2 per ton of urea produced. Thus, the results show that this waste-to-urea (WtU) technology is both economically valuable and environmentally advantageous (in terms of saving resources and limiting carbon footprint) for the production of chemicals from municipal solid waste in comparison with both the production of urea with conventional technology (starting from natural gas) and the use of RdF to produce electrical energy (waste-to-energy). A further benefit is the lower environmental impact of the solid residue produced from RdF conversion. The further benefit of this technology is the possibility to realize distributed fertilizer production. © 2017 Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

Preliminary experiments on wastes degradation by thermal plasma

International Nuclear Information System (INIS)

Cota S, G.; Pacheco S, J.; Segovia R, A.; Pena E, R.; Merlo S, L.

1996-01-01

This work presents the fundamental aspects involved in the installation and start up of an experimental equipment for the hazardous wastes degradation using the thermal plasma technology. It is mentioned about the form in which the thermal plasma is generated and the characteristics that its make to be an appropriate technology for the hazardous wastes degradation. Just as the installed structures for to realize the experiments and results of the first studies on degradation, using nylon as problem sample. (Author)

Estimation of Waste Quantities Using DeCAT-Pro

Energy Technology Data Exchange (ETDEWEB)

Yun, Taesik; Jung, Hyejin; Oh, Jaeyoung; Kim, Younggook [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

The D and D (Dismantling and Decontamination) is scheduled to get started in June 2022 elapsing five years of cooling spent fuels down. The final site status is postulated as Brown Field and tentative DCGL of less than 0.1 mSv per year to evaluate waste quantities in a conservative manner. The decommissioning strategy was determined the immediate decommissioning whose whole period would be taken for approximately 15 years; pre-decommissioning for two years, spent fuel cool-down for five years, D and D for six years, site remediation for two years. The assumption to dismantle the underground facilities including SSCs is to one meter beneath the ground level and the other facilities remain intact. In addition, non-radioactive concrete wastes would be used to landfill gaps of the remaining facilities. Although there are many assumptions we applied, the methodologies developed and the data produced by this research will play a meaningful role as a good starting point for the Kori-1 decommissioning after its shutdown to logically and reasonably estimate the waste quantity. However it is clear that tenacious efforts should be taken to successfully perform the decommissioning project.

Management of small producers waste in Slovenia

International Nuclear Information System (INIS)

Fabjan, Marija; Rojc, Joze

2007-01-01

Available in abstract form only. Full text of publication follows: Radioactive materials are extensively used in Slovenia in various fields and applications in medicine, industry and research. For the managing of radioactive waste raised from these establishments the Agency for radwaste management (ARAO) was authorised as the state public service of managing the radioactive waste in 1999. The public service of the radioactive waste of small producers in Slovenia is performed in line with the Governmental decree on the Mode, Subject and Terms of Performing the Public Service of Radioactive Waste Management (Official Gazette RS No. 32/99). According to the Decree the scope of the public service includes: 'collection of the waste from small producers at the producers' premises and its transportation to the storage facility for treatment, storing and disposal', 'acceptance of radioactive waste in case of emergency situation on the premises, in case of transport accidents or some other accidents', 'acceptance of radioactive waste in cases when the producer is unknown', 'management (collection, transport, pre-treatment, storing, together with QA and radiation protection measures) of radioactive waste', 'treatment and conditioning of radioactive waste for storing and disposal', and 'operating of the Central Interim Storage for LIL waste from small producers'. After taking over the performing of the public service, ARAO first started with the project for refurbishment and modernization of the Central Interim Storage Facility, including improvements of the storage utilization and rearrangement of the stored waste. (authors)

Waste-acceptance criteria for greater confinement disposal

International Nuclear Information System (INIS)

Gilbert, T.L.; Meshkov, N.K.

1987-01-01

A methodology for establishing waste-acceptance criteria based on quantitative performance factors that characterize the confinement capabilities of a waste disposal site and facility has been developed. The methodology starts from the basic objective of protecting public health and safety by providing assurance that disposal of the waste will not result in a radiation dose to any member of the general public, in either the short or long term, in excess of an established basic dose limit. The method is based on an explicit, straight-forward, and quantitative relationship among individual risk, confinement capabilities, and waste characteristics. A key aspect of the methodology is introduction of a confinement factor that characterizes the overall confinement capability of a particular facility and can be used for quantitative assessments of the performance of different disposal sites and facilities, as well as for establishing site-specific waste acceptance criteria. Confinement factors are derived by means of site-specific pathway analyses. They make possible a direct and simple conversion of a basic dose limit into waste-acceptance criteria, specified as concentration limits on radionuclides in the waste streams and expressed in quantitative form as a function of parameters that characterize the site, facility design, waste containers, and waste form. Waste acceptance criteria can be represented visually as activity/time plots for various waste streams. These plots show the concentrations of radionuclides in a waste stream as a function of time and permit a visual, quantitative assessment of long-term performance, relative risks from different radionuclides in the waste stream, and contributions from ingrowth. 13 references, 7 figures

Waste-acceptance criteria for greater-confinement disposal

International Nuclear Information System (INIS)

Gilbert, T.L.; Meshkov, N.K.

1986-01-01

A methodology for establishing waste-acceptance criteria based on quantitative performance factors that characterize the confinement capabilities of a waste-disposal site and facility has been developed. The methodology starts from the basic objective of protecting public health and safety by providing assurance that dispsoal of the waste will not result in a radiation dose to any member of the general public, in either the short or long term, in excess of an established basic dose limit. The method is based on an explicit, straightforward, and quantitative relationship among individual risk, confinement capabilities, and waste characteristics. A key aspect of the methodology is the introduction of a confinement factor that characterizes the overall confinement capability of a particular facility and can be used for quantitative assessments of the performance of different disposal sites and facilities, as well as for establishing site-specific waste-acceptance criteria. Confinement factors are derived by means of site-specific pathway analyses. They make possible a direct and simple conversion of a basic dose limit into waste-acceptance criteria, specified as concentration limits on radionuclides in the waste streams and expressed in quantitative form as a function of parameters that characterize the site, facility design, waste containers, and waste form. Waste-acceptance criteria can be represented visually as activity/time plots for various waste streams. These plots show the concentrations of radionuclides in a waste stream as a function of time and permit a visual, quantitative assessment of long-term performance, relative risks from different radionuclides in the waste stream, and contributions from ingrowth. 13 refs

PHYSICAL, CHEMICAL, AND STRUCTURAL EVOLUTION OF ZEOLITE-CONTAINING WASTE FORMS PRODUCED FROM METAKAOLINITE AND CALCINED HLW

International Nuclear Information System (INIS)

Pareizs, J. M.; Jantzenm, C.M.

2000-01-01

Natural and synthetic zeolites are extremely versatile materials. They can adsorb a variety of liquids and gases, and also take part in cation exchange reactions. Zeolites have the ability to sequester ions in lattice positions or within their networks of channels and voids. The zeolites can host alkali, alkaline earth and a variety of higher valance cations. As such they may be a viable alternative for immobilization of low activity waste (LAW) salts and calcines. The process for synthesizing zeolites is well documented for pure starting materials. A reactive aluminosilicate is reacted with an alkaline hydroxide at low temperature (<300 C) to form a zeolite. Processing time and temperature and specific reactants determine the type of zeolite formed. Zeolites are easy to make, and can be synthesized from a wide variety of natural and man made materials. However, relatively little is known about the process if one of the starting materials is a poorly characterized complex mixture of oxides (waste) containing nearly every element in the periodic table. The purpose of this work is to develop a clearer understanding of the advantages and limitations of producing a zeolite waste form from radioactive waste. Dr. M. W. Grutzeck at the Pennsylvania State University is investigating the production of a zeolite waste form using nonradioactive simulants. Dr. C. M. Jantzen and J. M. Pareizs at the Savannah River Technology Center will use the results from simulant work as a starting point for producing a zeolite waste form from an actual Savannah River Site radioactive waste stream

Physical, chemical, and structural evolution of zeolite-containing waste forms produced from metakaolinite and calcined HLW

International Nuclear Information System (INIS)

Pareizs, J.M.

2000-01-01

Natural and synthetic zeolites are extremely versatile materials. They can adsorb a variety of liquids and gases, and also take part in cation exchange reactions. Zeolites have the ability to sequester ions in lattice positions or within their networks of channels and voids. The zeolites can host alkali, alkaline earth and a variety of higher valence cations. As such they may be a viable alternative for immobilization of low activity waste (LAW) salts and calcines. The process for synthesizing zeolites is well documented for pure starting materials. A reactive aluminosilicate is reacted with an alkaline hydroxide at low temperature to form a zeolite. Processing time and temperature and specific reactants determine the type of zeolite formed. Zeolites are easy to make, and can be synthesized from a wide variety of natural and man made materials. However, relatively little is known about the process if one of the starting materials is a poorly characterized complex mixture of oxides (waste) containing nearly every element in the periodic table. The purpose of this work is to develop a clearer understanding of the advantages and limitations of producing a zeolite waste form from radioactive waste. Dr. M. W. Grutzeck at the Pennsylvania State University is investigating the production of a zeolite waste form using non-radioactive simulants. Dr. C. M. Jantzen and J. M. Pareizs at the Savannah River Technology Center will use the results from simulant work as a starting point for producing a zeolite waste form from an actual Savannah River Site radioactive waste stream

Status of waste form testing

International Nuclear Information System (INIS)

Lawroski, H.

1984-01-01

The promulgation of the amendment of 10 CFR Part 61 by the Nuclear Regulatory Commission of December 27, 1982 by Federal Register Notice with an effective date of December 27, 1983 established the criteria for licensing requirements, paragraph 60.56, contained the description to provide adequate stability of the site through the use of suitable waste forms. In May, 1983, the NRC published a final Branch Technical Position (BTP) paper on waste form. The position taken by the BTP was considerably more severe than indicated in 10 CFR Part 61. An extensive and expensive testing program was started in 1983. As an interim measure, the presently utilized solidification processes such as cement, Dow binder, Envirostone and bitumen, and the presently qualified High Integrity containers (HICs) were considered acceptable with the caveat that acceptable process control programs were being utilized. The NRC requested that topical reports for licenses be submitted. The topical reports were to contain test results to substantiate the acceptability of the waste forms. The test results to date show that the volume of wastes will have to increase to meet the position taken by the NRC in the BTP. This position will cause more waste to be generated which is contrary to the emphasis by states and others to reduce the volume of waste. The details of testing will be discussed in the paper to be presented

Hanford Waste Vitrification Plant - the project and process systems

International Nuclear Information System (INIS)

Swenson, L.D.; Miller, W.C.; Smith, R.A.

1990-01-01

The Hanford Waste Vitrification Plant (HWVP) project is scheduled to start construction on the Hanford reservation in southeastern Washington State in 1991. The project will immobilize the liquid high-level defense waste stored there. The HWVP represents the third phase of the U.S. Department of Energy (DOE) activities that are focused on the permanent disposal of high-level radioactive waste, building on the experience of Defense Waste Processing Facility (DWPF) at the Savannah River site, South Carolina, and of the West Valley Demonstration Plant (WVDP), New York. This sequential approach to disposal of the country's commercial and defense high-level radioactive waste allows HWVP to make extensive use of lessons learned from the experience of its predecessors, using mature designs from the earlier facilities to achieve economies in design and construction costs while enhancing operational effectiveness

Unlocking the resource potential of organic waste: a South African perspective

CSIR Research Space (South Africa)

Greben, HA

2009-10-01

Full Text Available ) resource rather than a waste material (DiStefano & Ambulkar 2006). It does, however, seem that the thinking around biolog- ical treatment of waste for energy recovery in South Africa is starting to change. A biogas digester converting human waste... of cost from a material treatment point of view. If energy is however a main driver, capital cost per unit energy recovered is a bet- ter measure. Capital cost per kW electrical export capacity gives an indication of the technology’s effectiveness as a...

Cross-flow filtration during the washing of a simulated radioactive waste stream

International Nuclear Information System (INIS)

MARK R., DUIGNAN

2005-01-01

Bechtel National, Inc. has been contracted by the Department of Energy to design a Waste Treatment and Immobilization Plant (WTP) to stabilize liquid radioactive waste that is stored at the Hanford Site as part of the River Protection Project (RPP). Because of its experience with radioactive waste stabilization, the Savannah River National Laboratory (SRNL) of the Westinghouse Savannah River Company is working with Bechtel and Washington Group International, to help design and test certain parts of the waste treatment facility. One part of the process is the separation of radioactive solids from the liquid wastes by cross-flow ultrafiltration. To test this process a cross-flow filter was used that was prototypic in porosity, length, and diameter, along with a simulated radioactive waste slurry, made to prototypically represent the chemical and physical characteristics of a Hanford waste in tank 241-AY-102/C-106. To mimic the filtration process the waste slurry undergoes several steps, including dewatering and washing. During dewatering the concentration of undissolved solids (UDS) of the simulated AY102/C106 waste is increased from 12 wt percent to at least 20 wt percent. Once at the higher concentration the waste must be washed to prepare for its eventual receipt in a High Level Radioactive Waste Melter to be vitrified. This paper describes the process of washing and filtering a batch of concentrated simulated waste in two cycles, which each containing 22 washing steps that used approximately 7.7 liters of a solution of 0.01 M NaOH per step. This will be the method used by the full-scale WTP to prepare the waste for vitrification. The first washing cycle started with the simulated waste that had a solids concentration of 20 wt percent UDS. This cycle began with a permeate filter flux of 0.015 gpm/ft2 (3.68 cm/hr) at 19.6 wt percent UDS with a density of 1.33 kg/L, and yield stress of 8.5 Pa. At the end of the 22 washing steps the permeate filter flux increased to

Construction of solid waste form test facility

International Nuclear Information System (INIS)

Park, Hyun Whee; Lee, Kang Moo; Koo, Jun Mo; Jung, In Ha; Lee, Jong Ryeul; Kim, Sung Whan; Bae, Sang Min; Cho, Kang Whon; Sung, Suk Jong

1989-02-01

The Solid Waste Form Test Facility (SWFTF) is now construction at DAEDUCK in Korea. In SWFTF, the characteristics of solidified waste products as radiological homogeneity, mechanical and thermal property, water resistance and lechability will be tested and evaluated to meet conditions for long-term storage or final disposal of wastes. The construction of solid waste form test facility has been started with finishing its design of a building and equipments in Sep. 1984, and now building construction is completed. Radioactive gas treatment system, extinguishers, cooling and heating system for the facility, electrical equipments, Master/Slave manipulator, power manipulator, lead glass and C.C.T.V. has also been installed. SWFTF will be established in the beginning of 1990's. At this report, radiation shielding door, nondestructive test of the wall, instrumentation system for the utility supply system and cell lighting system are described. (Author)

Independent technical review of Savannah River Site Defense Waste Processing Facility technical issues

International Nuclear Information System (INIS)

1992-07-01

The Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) will vitrify high-level radioactive waste that is presently stored as liquid, salt-cake, and sludge in 51 waste-storage tanks. Construction of the DWPF began in 1984, and the Westinghouse Savannah Company (WSRC) considers the plant to be 100% turned over from construction and 91% complete. Cold-chemical runs are scheduled to begin in November 1992, and hot start up is projected for June 1994. It is estimated that the plant lifetime must exceed 15 years to complete the vitrification of the current, high-level tank waste. In a memo to the Assistant Secretary for Defense Programs (DP-1), the Assistant Secretary for Environmental Restoration and Waste management (EM-1) established the need for an Independent Technical Review (ITR), or the Red Team, to ''review process technology issues preventing start up of the DWPF.'' This report documents the findings of an Independent Technical Review (ITR) conducted by the Department of Energy (DOE), Office of Environmental Restoration and Waste Management (EM), at the request of the Assistant Secretary for Environmental Restoration and Waste Management, of specified aspects of Defense Waste Process Facility (DWPF) process technology. Information for the assessment was drawn from documents provided to the ITR Team by the Westinghouse Savannah River Company (WSRC), and presentations, discussions, interviews, and tours held at the Savannah River Site (SRS) during the weeks of February and March 9, 1992

Why START?

International Nuclear Information System (INIS)

Mendelsohn, J.

1991-01-01

Barring some major unexpected downturn in US-Soviet relations, it seems likely that the long-awaited Strategic Arms Reduction Talks (START) treaty will be signed sometime in 1991. Under negotiation for the past nine years, public acceptance and Senate approval of a START treaty will be facilitated by the generally less confrontational East-West relationship which has evolved over that time, by the growing constraints on the US defense budget, and by the obvious merits of the treaty itself. Not only will the nearly complete START treaty be an extremely useful and powerful arms control agreement, it is also decidedly advantageous to US security interests. First and foremost, a START treaty will cap and reduce the steady buildup of nuclear weapons that has characterized the last 30 years of the US-Soviet strategic relationship. As a result of the basic outline originally agreed to at the Reykjavik summit, START will take a 25 to 35 percent bite out of existing nuclear arsenals, impose approximately a 50 percent cut in overall Soviet ballistic missile warheads and throw-weight (lifting power or payload capacity), and produce an exact 50 percent cut in Soviet SS-18 missiles

From Head Start to Sure Start: Reflections on Policy Transfer

Science.gov (United States)

Welshman, John

2010-01-01

This article uses the history of debates over the US Head Start programme (1965), Early Head Start (1994) and the UK Sure Start initiative (1998), as a window on to policy transfer. In all the three, the aim was that early intervention could offer a means of boosting children's educational attainment and of countering the wider effects of poverty…

Anaerobic digestion of cellulosic wastes

International Nuclear Information System (INIS)

Donaldson, T.L.; Lee, D.D.

1984-01-01

Anaerobic digestion is a potentially attractive technology for volume reduction of cellulosic wastes. A substantial fraction of the waste is converted to off-gas and a relatively small volume of biologically stabilized sludge is produced. Process development work is underway using a 75-L digester to verify rates and conversions obtained at the bench scale, to develop start-up and operating procedures, and to generate effluent for characterization and disposal studies. Three runs using batch and batch-fed conditions have been made lasting 36, 90, and over 200 days. Solids solubilization and gas production rates and total solids destruction have met or exceeded the target values of 0.6 g cellulose per L of reactor per day, 0.5 L off-gas per L of reactor per day, and 80% destruction of solids, respectively. Successful start-up procedures have been developed, and preliminary effluent characterization and disposal studies have been done. A simple dynamic process model has been constructed to aid in further process development and for use in process monitoring and control of a large-scale digester. 7 references, 5 figures, 1 table

Costs of the final disposal of radioactive wastes

International Nuclear Information System (INIS)

Drasdo, P.

2001-01-01

The study on the costs of radioactive waste disposal covers the topic of national concepts for the countries Germany, France, United Kingdom, Sweden, Switzerland and Unites States of America. The introduction into the topic of radioactive waste disposal is concerned with the classification of radioactive wastes, the safety of final repositories and the different concepts of final disposal. The used methods of data acquisition and data processing are described. The study compares the national final disposal concepts in order to identify the reasons for the differences in capital costs and annuity costs in the respective countries. The final chapter is concerned with the optimum timing for the start-up of operation of final repositories

Warehouse hazardous and toxic waste design in Karingau Balikpapan

Science.gov (United States)

Pratama, Bayu Rendy; Kencanawati, Martheana

2017-11-01

PT. Balikpapan Environmental Services (PT. BES) is company that having core business in Hazardous and Toxic Waste Management Services which consisting storage and transporter at Balikpapan. This research starting with data collection such as type of waste, quantity of waste, dimension area of existing building, waste packaging (Drum, IBC tank, Wooden Box, & Bulk Bag). Processing data that will be done are redesign for warehouse dimension and layout of position waste, specify of capacity, specify of quantity, type and detector placement, specify of quantity, type and fire extinguishers position which refers to Bapedal Regulation No. 01 In 1995, SNI 03-3985-2000, Employee Minister Regulation RI No. Per-04/Men/1980. Based on research that already done, founded the design for warehouse dimension of waste is 23 m × 22 m × 5 m with waste layout position appropriate with type of waste. The necessary of quantity for detector on this waste warehouse design are 56 each. The type of fire extinguisher that appropriate with this design is dry powder which containing natrium carbonate, alkali salts, with having each weight of 12 Kg about 18 units.

Getting waste program in motion again

International Nuclear Information System (INIS)

Kraft, S.P.

1989-01-01

The nation's electric ratepayers have invested some $4 billion since 1983 to finance a nuclear waste storage facility and have little to show for it says the author. DOE's waste management program has been characterized by missed deadlines, schedule delays, bureaucratic entanglements, and lost opportunities he charges. Utilities are concerned by both the lack of progress and DOE's seeming lack of concern for the costs that the delays are imposing on electric utilities and electricity consumers. He believes it is imperative that DOE get the waste management program back on track, and he offers a 5-point strategy to accomplish that objective: strengthen and improve DOE management and operations; proceed aggressively with the start of new site-characterization work; restore the monitored retrievable storage option; streamline the licensing process; and determine the suitability of Yucca Mountain as early as possible

Waste removal sequencing using ProdMod

International Nuclear Information System (INIS)

Paul, P.K.; Gregory, M.V.; Davis, N.R.; Brooke, J.N.

1996-01-01

The Savannah River Site (SRS) is starting to solidify its accumulated high-level radioactive waste into borosilicate glass in stainless steel canisters for eventual permanent storage. The in-tank precipitation process (ITP) and extended sludge processing (ESP) are two key operations in the waste processing complex. The supernate and dissolved salt from the waste storage tanks are transferred to the ITP process tank where the solution is decontaminated in batch processes. Soluble radioactive cesium is precipitated with sodium tetraphenylborate and strontium, uranium, and plutonium are adsorbed on monosodium titanate. The precipitate and adsorbent solids, which now contain the radionuclides, are concentrated using crossflow filters. The concentrated solids are sent to the high-level waste vitrification process. The decontaminated salt solution is sent to the low-level waste solidification process to form cement grout. In parallel with the precipitate operations, insoluble sludges that settled originally to the bottom of the waste tanks are reslurried and sent to ESP to undergo washing to reduce soluble salt content and aluminum dissolution, if required. In the vitrification process in the Defense Waste Processing Facility (DWPF), the concentrated precipitate from the ITP is mixed with the washed sludge from ESP and glass frit in proportion to form a stable borosilicate glass. A novel and fast-running Production Planning Model (ProdMod) has been developed to simulate the waste processing operation. This paper describes the application of ProdMod in sequencing the ITP batches and scheduling the ESP batches

Drypac-ing waste away at Sellafield

International Nuclear Information System (INIS)

Anon.

1997-01-01

The Sellafield Drypac Plant (SDP) is designed to treat intermediate level wastes stored on the Sellafield site in the UK. SDP is a key component in the overall strategy of encapsulating ILW for future disposal in an underground repository. Civil work on the plant has started and it is scheduled to begin active operations in 2002. (UK)

Chapter 7. Radioactive wastes

International Nuclear Information System (INIS)

2000-01-01

The inspection and assessment activities of Nuclear Regulatory Authority of the Slovak Republic (UJD) focused on minimization of activity and the quantity of produced radioactive waste (RAW), and on increasing safety of waste management. The general scheme of rad-waste management in the Slovak Republic is presented. The radioactive wastes produced during the operation of NPP V-1, NPP V-2 and NPP Mochovce in 1999 are listed.Liquid RAW was treated and conditioned into a solid form at the nuclear facility Technology for treatment and conditioning of RAW. In 1999 combustible solid waste was treated at the nuclear facility Incinerator of VUJE Trnava. Produced liquid and solid RAW are stored at designed equipment at individual nuclear installations (in case of NPP V-1, NPP V-2 Bohunice and NPP Mochovce in compliance with the Regulation No. 67/1987 Coll. law).The status of free capacity of these storages as of 31.121999 is presented. Storage solidified product built the SE-VYZ was fully filled at the end of 1999. In 1999 there was a significant improvement in the process of radioactive waste management by: (A) issuing approval for commissioning the National Repository for RAW, (B) issuing approval for commissioning the Treatment and Conditioning Center for RAW, (C) having the application for approval to transport conditioned RAW to the National repository Mochovce in the final stage of evaluation. At the beginning of 2000 it is realistic to expect that RAW conditioned in the Conditioning center of RAW will start to be disposed at the National repository of RAW in Mochovce

Solving the geologic issues in nuclear waste disposal

International Nuclear Information System (INIS)

Towse, D.

1979-01-01

Technical problems with nuclear waste disposal are largely geological. If these are not solved, curtailment of nuclear power development may follow, resulting in loss of an important element in the national energy supply. Present knowledge and credible advances are capable of solving these problems provided a systems view is preserved and a national development plan is followed. This requires identification of the critical controllable elements and a systematic underground test program to prove those critical elements. Waste migration can be understood and controlled by considering the key elements in the system: the system geometry, the hydrology, and the waste-rock-water chemistry. The waste program should: (1) identify and attack the critical problems first; (2) provide tests and demonstration at real disposal sites; and (3) schedule elements with long lead-times for early start and timely completion

The Net Enabled Waste Management Database in the context of an indicator of sustainable development for radioactive waste management

International Nuclear Information System (INIS)

Csullog, G.W.; Selling, H.; Holmes, R.; Benitez, J.C.

2002-01-01

The IAEA was selected by the UN to be the lead agency for the development and implementation of indicators of sustainable development for radioactive waste management (ISD-RW). Starting in late 1999, the UN initiated a program to consolidate a large number of indicators into a smaller set and advised the IAEA that a single ISD-RW was needed. In September 2001, a single indicator was developed by the IAEA and subsequently revised in February 2002. In parallel with its work on the ISD-RW, the IAEA developed and implemented the Net Enabled Waste Management Database (NEWMDB). The NEWMDB is an international database to collect, compile and disseminate information about nationally-based radioactive waste management programmes and waste inventories. The first data collection cycle with the NEWMDB (July 2001 to March 2002) demonstrated that much of the information needed to calculate the ISD-RW could be collected by the IAEA for its international database. However, the first data collection cycle indicated that capacity building, in the area of identifying waste classification schemes used in countries, is required. (author)

Let’s limit our waste production and let’s’ sort it!

CERN Multimedia

HSE Unit

2013-01-01

Let’s limit our waste production! – Why ? Preventing the production of waste is the best solution to avoid environmental issues, economic impacts and technical constraints. So, whenever you are involved in the design, manufacturing, distribution, use or dismantling of a product or an activity in general, always remember that the best waste is that which is not produced. The limitation of waste production being an HSE objective declared in 2013 by the CERN Director-General, we encourage everyone to help limit the amount of waste produced through CERN activities. Let’s sort it! – Why ? Since the 90s, CERN has implemented a policy to promote recovery of the waste* generated by its activities. Nowadays, CERN is committed to continuously improving its sorting and recovery and therefore various initiatives have been started by GS-IS to improve the recovery of waste (e.g. recovery of organic waste from restaurants; implementation of solar trash compactors - see Bulletin 27-...

Asia/Pacific moves to address mountainous waste problem

International Nuclear Information System (INIS)

Chynoweth, E.

1993-01-01

There is a serious lack of chemical waste treatment units in the Asia/Pacific region. In many countries a lack of infrastructure, coupled with scant or no legislation or enforcement, results in significant amounts of chemical waste being dumped without proper treatment. The exception is Japan, which has substantial incineration, treatment, and landfill capabilities. Japan's chemical industry generates more than 14 million m.t./year of waste, which is reduced to 2.51 million m.t./year after treatment and recycling. Chemical companies operating in Asia/Pacific countries that do not have authorized waste contractors and disposal plants have few options. They can treat wastes inhouse, increase recycling, ship wastes outside for treatment, or store wastes onsite. Some companies, such as Monsanto (St. Louis), claim to have managed to avoid producing any final wastes. The company's farm chemicals plant in Malaysia is one example - even the drums used to transport raw materials to the site have been replaced with returnable containers. Chiba (Basel) also has invested in cutting waste. The Swiss firm's dyestuffs plant at Candra Sari, Indonesia cut primary pollution by 90%, while product output rose 12% - a result of changing operations procedures and capital investment of only $6,500. A number of countries have started to address the industrial waste problem - foremost is Hong Kong, which is currently commissioning one of the first chemical waste treatment centers in the region. Other countries planning integrated waste treatment facilities include Indonesia, Malaysia, Australia, Thailand, Singapore, and China

Managing radioactive waste safely. Proposals for developing a policy for managing solid radioactive waste in the UK

International Nuclear Information System (INIS)

2001-09-01

More than 10,000 tonnes of radioactive waste are safely stored in the UK, but await a decision on their long-term future. This will increase to 250,000 tonnes when nuclear material currently in use is converted into solid waste. Even if no new nuclear power plants are built and reprocessing of spent nuclear fuel ends when existing plants reach the end of their working lives, about another 250,000 tonnes of waste will arise during the clean-up of those plants over the next century. Most of this waste results from the work of Government agencies or publicly owned companies since the 1940s. Some of the substances involved will be radioactive and potentially dangerous for hundreds of thousands of years. There are much larger amounts of low-level (less radioactive) waste. Currently, these are disposed of at a special surface repository in Cumbria. But again, much larger amounts will arise as existing nuclear facilities are cleaned up. We must decide how to manage this waste in the long term. Implementing that decision will take decades. So now is the time to start planning for our future. In this paper, the UK Government and the Devolved Administrations for Scotland, Wales and Northern Ireland are launching a national debate which will lead up to that decision, and beyond it. The aim is to develop, and implement, a UK nuclear waste management programme which inspires public support and confidence. To do this, we propose a major programme of research and public discussion, using many techniques - some traditional, some relatively new - to stimulate informed discussion, and to involve as many people and groups as possible. We want to inspire public confidence in the decisions and the way in which they are implemented. To do that, we have to demonstrate that all options are considered; that choices between them are made in a clear and logical way; that people's values and concerns are fully reflected in this process; and that information we provide is clear, accurate

Solid waste management in Khartoum industrial area

International Nuclear Information System (INIS)

Elsidig, N. O. A.

2004-05-01

This study was conducted in Khartoum industrial area (KIA). The study discusses solid waste generation issues in KIA as well as solid waste collection, storage, transport and final disposal methods. A focus on environmental impact resulting from the accumulation of solid waste was presented by reviewing solid waste management in developed as well as developing countries starting from generation to final disposal. Environmental health legislation in Sudan was investigated. The study covers all the (eight) industrial sub-sectors presented in KIA. The main objective of the study is to assess the situation of solid waste in KIA. To fulfill the objectives of the study the researcher deemed it necessary to explore problems related to solid waste generation and solid waste arrangement with special emphasis on final disposal methods. Practically, 31 (thirty-one) factories representing the different industrial sub-sectors in KIA were studied. This represents 25% of the total number of factories located in KIA. Data were obtained by, questionnaires, interviews and observations mainly directed to concerned officials, solid waste workers, pickers and brokers. Obtained data were stored, coded, tabulated and analyzed using the computer systems (excel and SPSS programmes). The obtained results should clear deficiency in the management of solid waste which led to great environmental deterioration in KIA and neighboring residential areas. The environment in studied area is continuously polluted due to high pollution loads and unproved solid waste management. In order to maintain health environment operating factories have to pretreated their solid waste according to the recognized standards and waste minimization techniques such as recycling and re use should be widely applied, moreover, running crash programme for environmental sanitation in Khartoum state should be expanded and improved to include special characteristics of solid waste from industries. Finally, increase awareness

Defense waste processing facility startup progress report

International Nuclear Information System (INIS)

Iverson, D.C.; Elder, H.H.

1992-01-01

The Savannah River Site (SRS) has been operating a nuclear fuel cycle since the 1950's to produce nuclear materials in support of the national defense effort. About 83 million gallons of high level waste produced since operation began have been consolidated into 33 million gallons by evaporation at the waste tank farm. The Department of Energy has authorized the construction of the Defense Waste Processing Facility (DWPF) to immobilize the waste as a durable borosilicate glass contained in stainless steel canisters, prior to emplacement in a federal repository. The DWPF is now mechanically complete and undergoing commissioning and run-in activities. Cold startup testing using simulated non-radioactive feeds is scheduled to begin in November 1992 with radioactive operation scheduled to begin in May 1994. While technical issues have been identified which can potentially affect DWPF operation, they are not expected to negatively impact the start of non-radioactive startup testing

Development of recycling techniques on decommissioning concrete waste

International Nuclear Information System (INIS)

Ishikura, Takeshi; Oguri, Daiichiro; Sukekiyo, Mitsuaki

2000-01-01

Nuclear Power Engineering Corporation (NUPEC) has been developing decommissioning techniques, implemented under a contract with the Ministry of International Trade and Industry (MITI), to verify and improve the performance of the key decommissioning techniques. One of main themes is on concrete recycling techniques, which deals with high quality aggregate retrieval from concrete waste, high efficient usage of the by-product powder to recycling products, and effective usage of radioactive concrete to filling material for waste form. This paper describes progress and accomplishment on the concrete recycling technique development which started in 1996. (author)

Smaller plates, less food waste

DEFF Research Database (Denmark)

Hansen, Pelle Guldborg; Schmidt, Karsten; Skov, Laurits Rhoden

With roughly one-third of food produced for human consumption lost or wasted globally (about 1.3 billion tons per year), the impact on the environment cannot be anymore neglected. Actions at all points in the production chain are now urgent, including reductions in food waste at home, by retailer...... the hypothesis that dishware size plays an important role in the amount of food wasted among Danish adults in a self-service eating setting. This finding has PHN implications: slight changes in the foodscape can contribute to sustainable food consumption goals.......With roughly one-third of food produced for human consumption lost or wasted globally (about 1.3 billion tons per year), the impact on the environment cannot be anymore neglected. Actions at all points in the production chain are now urgent, including reductions in food waste at home, by retailers...... and producers. Northern European consumers are among the most environmentally concerned consumers, however, their concerns do not always translate in more sustainable food-related behaviours. Furthermore, food choices are not always rational and could be non-reflective. Hence, the objective of this pilot study...

Operating document on management division waste management section in Tokai works in the 2002 fiscal year. Document on present of affairs

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)

The Cigeo project: an industrial storage site for radioactive wastes in deep underground

International Nuclear Information System (INIS)

Krieguer, Jean-Marie

2017-01-01

In 2006, France has decided to store its high-level and long-lived radioactive wastes, mostly issued from the nuclear industry, in a deep geological underground disposal site. This document presents the Cigeo project, a deep underground disposal site (located in the East of France) for such radioactive wastes, which construction is to be started in 2021 (subject to authorization in 2018). After a brief historical review of the project, started 20 years ago, the document presents the radioactive waste disposal context, the ethical choice of underground storage (in France and elsewhere) for these types of radioactive wastes, the disposal site safety and financing aspects, the progressive development of the underground facilities and, of most importance, its reversibility. In a second part, the various works around the site are presented (transport, buildings, water and power supply, etc.) together with a description of the various radioactive wastes (high and intermediate level and long-lived wastes and their packaging) that will be disposed in the site. The different steps of the project are then reviewed (the initial design and initial construction phases, the pilot industrial phase (expected in 2030), the operating phase, and the ultimate phases that will consist in the definitive closure of the site and its monitoring), followed by an extensive description of the various installations of surface and underground facilities, their architecture and their equipment

Radioactive waste and the back part of fuel cycle of nuclear installations in Slovakia

International Nuclear Information System (INIS)

Koprda, V.

2004-01-01

This article is devoted to radioactive waste (RAW) management, an integrated system starting with collection and sorting of RAW through its storage, treatment, conditioning, handling and transport up to its disposal. Some notes will touch also the near surface depository of low level and intermediate level radioactive waste in Mochovce, and the long-term storage of waste improper for such type of disposal, and also some words will be addressed to the development and research of a deep geological depository for disposal spent fuel from nuclear power plant and long-lived radioactive waste. (author)

Waste certification review program at the Savannah River Site

International Nuclear Information System (INIS)

Faulk, G.W.; Kinney, J.C.; Knapp, D.C.; Burdette, T.E.

1996-01-01

After approving the waste certification programs for 45 generators of low-level radioactive and mixed waste, Westinghouse Savannah River Company (WSRC) moved forward to implement a performance-based approach for assuring that approved waste generators maintain their waste certification programs. WSRC implemented the Waste Certification Review Program, which is comprised of two sitewide programs, waste generator self-assessments and Facility Evaluation Board reviews, integrated with the WSRC Solid Waste Management Department Waste Verification Program Evaluations. The waste generator self-assessments ensure compliance with waste certification requirements, and Facility Evaluation Board reviews provide independent oversight of generators' waste certification programs. Waste verification evaluations by the TSD facilities serve as the foundation of the program by confirming that waste contents and generator performance continue to meet waste acceptance criteria (WSRC 1994) prior to shipment to treatment, storage, and disposal facilities. Construction of the Savannah River Site (SRS) was started by the US Government in 1950. The site covers approximately 300 square miles located along the Savannah River near Aiken, South Carolina. It is operated by the US Department of Energy (DOE). Operations are conducted by managing and operating contractors, including the Westinghouse Savannah River Company (WSRC). Historically, the primary purpose of the SRS was to produce special nuclear materials, primarily plutonium and tritium. In general, low-level radioactive and mixed waste is generated through activities in operations. Presently, 47 SRS facilities generate low-level radioactive and mixed waste. The policies, guidelines, and requirements for managing these wastes are determined by DOE and are reflected in DOE Order 5820.2A (US DOE 1988)

Radioactive waste vitrification: A review

International Nuclear Information System (INIS)

Cole, L.L.; Fields, D.E.

1989-08-01

The research and development of an immobilization process for the containment of nuclear high-level liquid waste has been underway for well-over the past four decades. The method that has become the state-of-the-art is the liquid-fed ceramic melter process which converts a mixture of high-level liquid waste and glass forming frit to a borosilicate glass product. This report gives a chronological review of the various vitrification processes starting with the very first reported process in 1960. Information on the early methods of frit selection as well as information on the currently computerized method are presented. The importance of all these parameters is discussed with regard to product durability. 26 refs., 8 figs., 1 tab

Remediation and decommissioning of radioactive waste facilities in Estonia

International Nuclear Information System (INIS)

Putnik, H.; Realo, E.

2001-01-01

decommissioning and waste handling, e.g. creation of a waste treatment and conditioning facility, construction of an on-site interim storage for conditioned radioactive waste; Conditioning of solid operational waste in the dry storage and liquid waste tanks; Dismantling of contaminated installations; Declassification and demolition of useless facilities; Development of detailed decommissioning plans for the reactor systems. In the following short information is presented on the radioactive waste management and decommissioning projects carried out by ALARA Ltd at Paldiski after taking custody of the site. Project on conditioning of operational solid waste During the site operations solid radioactive waste was disposed in an on-site storage facility, SWS, which consisted of a concrete structure, divided into 10 cells. The former site operator has used three of these cells for storage of radioactive waste. Waste had been dumped into the facility without any conditioning or packaging and without any recorded inventory. The estimated waste volume in the SWS was about 100 m 3 including eight heat exchangers and 20 control rods from the repair and maintenance campaign of the reactor no I. The project started in 1996 with a radiological characterisation of the waste and continued with waste retrieval and conditioning. Depending on the radiological conditions, both remotely operated technique and manual retrieval was practiced. In summer 2000 the project was completed with demolition of the building after a full decontamination and declassification of the facility. During the project total 0.04 manSv was received by 16 persons, the maximum dose burden for a single person being 7.6 mSv. A more detailed description of this project was summarised in papers to international conferences WM'98 and ICEM'99. Project on conditioning of waste in liquid waste storage tanks Liquid radioactive waste was stored in the tanks of the Liquid Waste Treatment Facility (LWTF) and in the Liquid Waste Storage

Value chains for biorefineries of wastes from food production and services - ValueWaste

Energy Technology Data Exchange (ETDEWEB)

Kahiluoto, H.; Kuisma, M.; Knuuttila, M. (and others) (MTT Agrifood Research Finland, Mikkeli (Finland)). Email: helena.kahiluoto@mtt.fi

2010-10-15

The aim of the ValueWaste project is to analyse biomass potentials, appropriate technologies and business opportunities. Contrasting regional scenarios for biorefinery activities are developed, and their overall sustainability is assessed: environmental impacts using life cycle assessment, impacts on regional economy, partnership in actor chains, as well as business opportunities and possibilities for commercialisation are considered. South Savo and partly Satakunta provide the case study regions, but the project also produces tools for generalisation and contributes to national solutions. The theoretical potentials suggest that the agrifood waste has a significant and currently untapped potential for replacing non-renewable energy and recycling nutrients, and further for climate and water protection. The volume of agrifood waste varies mainly according to animal husbandry, crop production and food processing of a region. New business opportunities were found from the value chain of biowaste flows in the area of Etelae-Savo. Unexploited raw materials and new methods in waste collection and transportation offer entrepreneurial opportunities and decrease the costs of operation. Based on the conceptual work for creation of the contrasting regional biorefinery scenarios, performed in workshops for project and steering group members, four different optimisation starting points were determined: 1) replacement of fossil energy; 2) maximisation of carbon sequestration; 3) water protection and 4) enhancement of regional economy. Present situation of the biomass utilisation in the region was adopted as the baseline scenario. Four contrasting, consistent scenarios for the value chain of waste-based biorefineries are formed in South Savo. (orig.)

Deliverable D4.5. Failure Mode and Effect Analysis for 100% waste concrete. SUS-CON

NARCIS (Netherlands)

Visser, J.H.M.

2014-01-01

On January 1st 2012, the European project SUS-CON has been started: “SUStainable, innovative and energy efficient CONcrete, based on the integration of all waste materials” (grant agreement no: 285463). The SUS-CON project aims at developing new technology routes to integrate waste materials in the

Treatment of solid radioactive waste: The incineration of low level radioactive waste

International Nuclear Information System (INIS)

Dirks, F.; Hempelmann, W.

1982-01-01

Nuclear facilities produce large quantities of burnable solid radioactive waste which incineration can reduce in volume and change into a form capable of ultimate storage. Experiments over many years were carried out at the Karlsruhe Nuclear Research Center to determine the boundary conditions for the design and construction of incineration plants for radioactive waste. On the basis of those experiments a test facility was started up in 1971. This operating facility consists of a shaft furnace lined with ceramics with a downstream series of ceramic flue gas filters. In 1976 the plant was exchanged by the installation of a pilot facility for burning organic solvents and of a flue gas scrubber. The plant has so far been in operation for more than 28000 hours and has processed in excess of 1500 to of solid and some 300 m 3 of liquid low level radioactive wastes. Various repairs and interventions were carried out without greatly impairing availability, which was 81 % on the average. The plant design is being used by various licensees in Japan and Europe; three plants are either in operation or completed, three more are under construction or in the planning stage. On the basis of the available process an incineration plant for alpha contaminated waste will be built at the Karlsruhe Nuclear Research Center in the next few years. (orig.)

Immobilization of metal wastes by reaction with H2S in anoxic basins. Concept and Elaboration

NARCIS (Netherlands)

Schuiling, R.D.

2013-01-01

Metal wastes are produced in large quantities by a number of industries. Their disposal in isolated waste deposits is certain to cause many subsequent problems, because every material will sooner or later return to the geochemical cycle. The sealing of disposal sites usually starts to

Whose environment? Which perspective? A critical approach to hazardous waste management in Sweden

OpenAIRE

R Lidskog

1993-01-01

Starting with a description of six general interpretations of this kind of hazardous waste siting, and with a description of the policy for hazardous waste management in Sweden, the author examines the decisionmaking process regarding the siting of the central plant for hazardous waste in Sweden. The paper ends with the conclusion that a locational conflict is to be seen mainly as a struggle concerning the perception and definition of the issue. Thus the question is which perspective on the i...

Generation and management of waste electric vehicle batteries in China.

Science.gov (United States)

Xu, ChengJian; Zhang, Wenxuan; He, Wenzhi; Li, Guangming; Huang, Juwen; Zhu, Haochen

2017-09-01

With the increasing adoption of EVs (electric vehicles), a large number of waste EV LIBs (electric vehicle lithium-ion batteries) were generated in China. Statistics showed generation of waste EV LIBs in 2016 reached approximately 10,000 tons, and the amount of them would be growing rapidly in the future. In view of the deleterious effects of waste EV LIBs on the environment and the valuable energy storage capacity or materials that can be reused in them, China has started emphasizing the management, reuse, and recycling of them. This paper presented the generation trend of waste EV LIBs and focused on interrelated management development and experience in China. Based on the situation of waste EV LIBs management in China, existing problems were analyzed and summarized. Some recommendations were made for decision-making organs to use as valuable references to improve the management of waste EV LIBs and promote the sustainable development of EVs.

Waste Isolation Pilot Plant simulated RH TRU waste experiments: Data and interpretation pilot

International Nuclear Information System (INIS)

Molecke, M.A.; Argueello, G.J.; Beraun, R.

1993-04-01

The simulated, i.e., nonradioactive remote-handled transuranic waste (RH TRU) experiments being conducted underground in the Waste Isolation Pilot Plant (WIPP) were emplaced in mid-1986 and have been in heated test operation since 9/23/86. These experiments involve the in situ, waste package performance testing of eight full-size, reference RH TRU containers emplaced in horizontal, unlined test holes in the rock salt ribs (walls) of WIPP Room T. All of the test containers have internal electrical heaters; four of the test emplacements were filled with bentonite and silica sand backfill materials. We designed test conditions to be ''near-reference'' with respect to anticipated thermal outputs of RH TRU canisters and their geometrical spacing or layout in WIPP repository rooms, with RH TRU waste reference conditions current as of the start date of this test program. We also conducted some thermal overtest evaluations. This paper provides a: detailed test overview; comprehensive data update for the first 5 years of test operations; summary of experiment observations; initial data interpretations; and, several status; experimental objectives -- how these tests support WIPP TRU waste acceptance, performance assessment studies, underground operations, and the overall WIPP mission; and, in situ performance evaluations of RH TRU waste package materials plus design details and options. We provide instrument data and results for in situ waste container and borehole temperatures, pressures exerted on test containers through the backfill materials, and vertical and horizontal borehole-closure measurements and rates. The effects of heat on borehole closure, fracturing, and near-field materials (metals, backfills, rock salt, and intruding brine) interactions were closely monitored and are summarized, as are assorted test observations. Predictive 3-dimensional thermal and structural modeling studies of borehole and room closures and temperature fields were also performed

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)

High-level nuclear waste disposal

International Nuclear Information System (INIS)

Burkholder, H.C.

1985-01-01

The meeting was timely because many countries had begun their site selection processes and their engineering designs were becoming well-defined. The technology of nuclear waste disposal was maturing, and the institutional issues arising from the implementation of that technology were being confronted. Accordingly, the program was structured to consider both the technical and institutional aspects of the subject. The meeting started with a review of the status of the disposal programs in eight countries and three international nuclear waste management organizations. These invited presentations allowed listeners to understand the similarities and differences among the various national approaches to solving this very international problem. Then seven invited presentations describing nuclear waste disposal from different perspectives were made. These included: legal and judicial, electric utility, state governor, ethical, and technical perspectives. These invited presentations uncovered several issues that may need to be resolved before high-level nuclear wastes can be emplaced in a geologic repository in the United States. Finally, there were sixty-six contributed technical presentations organized in ten sessions around six general topics: site characterization and selection, repository design and in-situ testing, package design and testing, disposal system performance, disposal and storage system cost, and disposal in the overall waste management system context. These contributed presentations provided listeners with the results of recent applied RandD in each of the subject areas

Salt creep design consideration for underground nuclear waste storage

International Nuclear Information System (INIS)

Li, W.T.; Wu, C.L.; Antonas, N.J.

1983-01-01

This paper summarizes the creep consideration in the design of nuclear waste storage facilities in salt, describes the non-linear analysis method for evaluating the design adequacy, and presents computational results for the current storage design. The application of rock mechanics instrumentation to assure the appropriateness of the design is discussed. It also describes the design evolution of such a facility, starting from the conceptual design, through the preliminary design, to the detailed design stage. The empirical design method, laboratory tests and numerical analyses, and the underground in situ tests have been incorporated in the design process to assure the stability of the underground openings, retrievability of waste during the operation phase and encapsulation of waste after decommissioning

Optimization of the radioactive waste storage

International Nuclear Information System (INIS)

Dellamano, Jose Claudio

2005-01-01

Radioactive waste storage is the practice adopted in countries where the production of small quantities of radioactive waste does not justify the immediate investment in the construction of a repository. Accordingly, at IPEN, treated radioactive wastes, mainly solid compacted, have been stored for more than 20 years, in 200 dm 3 drums. The storage facility is almost complete and must be extended. Taking into account that a fraction of these wastes has decayed to a very low level due to the short half - life of some radionuclides and considering that 'retrieval for disposal as very low level radioactive waste' is one of the actions suggested to radioactive waste managers, the Laboratory of Waste Management of IPEN started a project to apply the concepts of clearance levels and exemption limits to optimize the radioactive waste storage capacity . This study has been carried out by determining the doses and costs related to two main options: either to maintain the present situation or to open the packages and segregate the wastes that may be subject to clearance, using the national, two international clearance levels and the annual public limit. Doses and costs were evaluated as well as the collective dose and the detriment cost. The analytical solution among the evaluated options was determined by using the technique to aid decision making known as cost-benefit analysis. At last, it was carried out the sensitivity analysis considering all criteria and parameters in order to assess the robustness of the analytical solution. This study can be used as base to other institutions or other countries with similar nuclear programs. (author)

Westinghouse waste simulation and optimization software tool

International Nuclear Information System (INIS)

Mennicken, Kim; Aign, Jorg

2013-01-01

Applications for dynamic simulation can be found in virtually all areas of process engineering. The tangible benefits of using dynamic simulation can be seen in tighter design, smoother start-ups and optimized operation. Thus, proper implementation of dynamic simulation can deliver substantial benefits. These benefits are typically derived from improved process understanding. Simulation gives confidence in evidence based decisions and enables users to try out lots of 'what if' scenarios until one is sure that a decision is the right one. In radioactive waste treatment tasks different kinds of waste with different volumes and properties have to be treated, e.g. from NPP operation or D and D activities. Finding a commercially and technically optimized waste treatment concept is a time consuming and difficult task. The Westinghouse Waste Simulation and Optimization Software Tool will enable the user to quickly generate reliable simulation models of various process applications based on equipment modules. These modules can be built with ease and be integrated into the simulation model. This capability ensures that this tool is applicable to typical waste treatment tasks. The identified waste streams and the selected treatment methods are the basis of the simulation and optimization software. After implementing suitable equipment data into the model, process requirements and waste treatment data are fed into the simulation to finally generate primary simulation results. A sensitivity analysis of automated optimization features of the software generates the lowest possible lifecycle cost for the simulated waste stream. In combination with proven waste management equipments and integrated waste management solutions, this tool provides reliable qualitative results that lead to an effective planning and minimizes the total project planning risk of any waste management activity. It is thus the ideal tool for designing a waste treatment facility in an optimum manner

High-Level Waste Vitrification Facility Feasibility Study

Energy Technology Data Exchange (ETDEWEB)

D. A. Lopez

1999-08-01

A ''Settlement Agreement'' between the Department of Energy and the State of Idaho mandates that all radioactive high-level waste now stored at the Idaho Nuclear Technology and Engineering Center will be treated so that it is ready to be moved out of Idaho for disposal by a compliance date of 2035. This report investigates vitrification treatment of the high-level waste in a High-Level Waste Vitrification Facility based on the assumption that no more New Waste Calcining Facility campaigns will be conducted after June 2000. Under this option, the sodium-bearing waste remaining in the Idaho Nuclear Technology and Engineering Center Tank Farm, and newly generated liquid waste produced between now and the start of 2013, will be processed using a different option, such as a Cesium Ion Exchange Facility. The cesium-saturated waste from this other option will be sent to the Calcine Solids Storage Facilities to be mixed with existing calcine. The calcine and cesium-saturated waste will be processed in the High-Level Waste Vitrification Facility by the end of calendar year 2035. In addition, the High-Level Waste Vitrification Facility will process all newly-generated liquid waste produced between 2013 and the end of 2035. Vitrification of this waste is an acceptable treatment method for complying with the Settlement Agreement. This method involves vitrifying the waste and pouring it into stainless-steel canisters that will be ready for shipment out of Idaho to a disposal facility by 2035. These canisters will be stored at the Idaho National Engineering and Environmental Laboratory until they are sent to a national geologic repository. The operating period for vitrification treatment will be from the end of 2015 through 2035.

High-Level Waste Vitrification Facility Feasibility Study

International Nuclear Information System (INIS)

D. A. Lopez

1999-01-01

A ''Settlement Agreement'' between the Department of Energy and the State of Idaho mandates that all radioactive high-level waste now stored at the Idaho Nuclear Technology and Engineering Center will be treated so that it is ready to be moved out of Idaho for disposal by a compliance date of 2035. This report investigates vitrification treatment of the high-level waste in a High-Level Waste Vitrification Facility based on the assumption that no more New Waste Calcining Facility campaigns will be conducted after June 2000. Under this option, the sodium-bearing waste remaining in the Idaho Nuclear Technology and Engineering Center Tank Farm, and newly generated liquid waste produced between now and the start of 2013, will be processed using a different option, such as a Cesium Ion Exchange Facility. The cesium-saturated waste from this other option will be sent to the Calcine Solids Storage Facilities to be mixed with existing calcine. The calcine and cesium-saturated waste will be processed in the High-Level Waste Vitrification Facility by the end of calendar year 2035. In addition, the High-Level Waste Vitrification Facility will process all newly-generated liquid waste produced between 2013 and the end of 2035. Vitrification of this waste is an acceptable treatment method for complying with the Settlement Agreement. This method involves vitrifying the waste and pouring it into stainless-steel canisters that will be ready for shipment out of Idaho to a disposal facility by 2035. These canisters will be stored at the Idaho National Engineering and Environmental Laboratory until they are sent to a national geologic repository. The operating period for vitrification treatment will be from the end of 2015 through 2035

Westinghouse waste simulation and optimization software tool

Energy Technology Data Exchange (ETDEWEB)

Mennicken, Kim; Aign, Jorg [Westinghouse Electric Germany GmbH, Hamburg (Germany)

2013-07-01

Applications for dynamic simulation can be found in virtually all areas of process engineering. The tangible benefits of using dynamic simulation can be seen in tighter design, smoother start-ups and optimized operation. Thus, proper implementation of dynamic simulation can deliver substantial benefits. These benefits are typically derived from improved process understanding. Simulation gives confidence in evidence based decisions and enables users to try out lots of 'what if' scenarios until one is sure that a decision is the right one. In radioactive waste treatment tasks different kinds of waste with different volumes and properties have to be treated, e.g. from NPP operation or D and D activities. Finding a commercially and technically optimized waste treatment concept is a time consuming and difficult task. The Westinghouse Waste Simulation and Optimization Software Tool will enable the user to quickly generate reliable simulation models of various process applications based on equipment modules. These modules can be built with ease and be integrated into the simulation model. This capability ensures that this tool is applicable to typical waste treatment tasks. The identified waste streams and the selected treatment methods are the basis of the simulation and optimization software. After implementing suitable equipment data into the model, process requirements and waste treatment data are fed into the simulation to finally generate primary simulation results. A sensitivity analysis of automated optimization features of the software generates the lowest possible lifecycle cost for the simulated waste stream. In combination with proven waste management equipments and integrated waste management solutions, this tool provides reliable qualitative results that lead to an effective planning and minimizes the total project planning risk of any waste management activity. It is thus the ideal tool for designing a waste treatment facility in an optimum manner

Lean start-up

DEFF Research Database (Denmark)

Rasmussen, Erik Stavnsager; Tanev, Stoyan

2016-01-01

The risk of launching new products and starting new firms is known to be extremely high. The Lean Start-up approach is a way of reducing these risks and enhancing the chances for success by validating the products and services in the market with customers before launching it in full scale. The ma...... and the final business model. In other words: The start-up must first nail the problem together with the customers, then develop the solution and test, and then in the end scale it to a full-grown business model.......The risk of launching new products and starting new firms is known to be extremely high. The Lean Start-up approach is a way of reducing these risks and enhancing the chances for success by validating the products and services in the market with customers before launching it in full scale. The main...

Swedish nuclear waste efforts

International Nuclear Information System (INIS)

Rydberg, J.

1981-09-01

After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981

Class start times, sleep, and academic performance in college: a path analysis.

Science.gov (United States)

Onyper, Serge V; Thacher, Pamela V; Gilbert, Jack W; Gradess, Samuel G

2012-04-01

Path analysis was used to examine the relationship between class start times, sleep, circadian preference, and academic performance in college-aged adults. Consistent with observations in middle and high school students, college students with later class start times slept longer, experienced less daytime sleepiness, and were less likely to miss class. Chronotype was an important moderator of sleep schedules and daytime functioning; those with morning preference went to bed and woke up earlier and functioned better throughout the day. The benefits of taking later classes did not extend to academic performance, however; grades were somewhat lower in students with predominantly late class schedules. Furthermore, students taking later classes were at greater risk for increased alcohol consumption, and among all the factors affecting academic performance, alcohol misuse exerted the strongest effect. Thus, these results indicate that later class start times in college, while allowing for more sleep, also increase the likelihood of alcohol misuse, ultimately impeding academic success.

Final Report for the Restart of the Waste Characterization, Reduction and Repackaging Facility (WCRRF) Contractor Readiness Assessment (CRA)

Energy Technology Data Exchange (ETDEWEB)

Stephens, Gregory Mark [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-02-22

The Los Alamos National Laboratory (LANL or Laboratory) Contractor Readiness Assessment (CRA) required for restart of the Technical Area (TA) 50 Waste Characterization, Reduction, and Repackaging Facility (WCRRF) for remediated nitrate salt (RNS) waste operations was performed in compliance with the requirements of Department of Energy (DOE) Order (O) 425.1D, Verification of Readiness to Start Up or Restart Nuclear Facilities, and LANL procedure FSD-115-001, Verification of Readiness to Start Up or Restart LANL Nuclear Facilities, Activities, and Operations.

Key parameters of the swimming start and their relationship to start performance.

Science.gov (United States)

Tor, Elaine; Pease, David L; Ball, Kevin A

2015-01-01

The swimming start is typically broken into three sub-phases; on-block, flight, and underwater phases. While overall start performance is highly important to elite swimming, the contribution of each phase and important technical components within each phase, particularly with the new kick-start technique, has not been established. The aim of this study was to identify technical factors associated with overall start performance, with a particular focus on the underwater phase. A number of parameters were calculated from 52 starts performed by elite freestyle and butterfly swimmers. These parameters were split into above-water and underwater groupings, before factor analysis was used to reduce parameter numbers for multiple regression. For the above-water phases, 81% of variance in start performance was accounted for by take-off horizontal velocity. For the underwater water phase, 96% of variance was accounted for with time underwater in descent, time underwater in ascent and time to 10 m. Therefore, developing greater take-off horizontal velocity and focussing on the underwater phase by finding the ideal trajectory will lead to improved start performance.

From START to NEW START. The dilemma and future of nuclear disarmament; Von START zu NEW START. Das Dilemma und die Zukunft der Nuklearen Abruestung

Energy Technology Data Exchange (ETDEWEB)

Plettenberg, Lars

2012-07-01

The report describes the existing four agreements on nuclear disarmament: START I (1991). START II (1993), SORT (2002) and NEW START (2010). The chapter on the dependence between nuclear disarmament and strategic stability covers the issues mutual assured destruction (MAD), credibility, overkill capacity; the role of nuclear weapons in the national strategies of the USA and NATO, Russia, Great Britain, France, China and the other nuclear states. Ways out of MAD include disarmament, de-alerting and mutual assured protection (MAP).

A review and overview of nuclear waste management

International Nuclear Information System (INIS)

Murray, R.L.

1984-01-01

An understanding of the status and issues in the management of radioactive wastes is based on technical information on radioactivity, radiation, biological hazard of radiation exposure, radiation standards, and methods of protection. The fission process gives rise to radioactive fission products and neutron bombardment gives activation products. Radioactive wastes are classified according to source: defense, commercial, industrial, and institutional; and according to physical features: uranium mill tailings, high-level, transuranic, and low-level. The nuclear fuel cycle, which contributes a large fraction of annual radioactive waste, starts with uranium ore, includes nuclear reactor use for electrical power generation, and ends with ultimate disposal of residues. The relation of spent fuel storage and reprocessing is governed by technical, economic, and political considerations. Waste has been successfully solidified in glass and other forms and choices of the containers for the waste form are available. Methods of disposal of high-level waste that have been investigated are transmutation by neutron bombardment, shipment to Antartica, deep-hole insertion, subseabed placement, transfer by rocket to an orbit in space, and disposal in a mined cavity. The latter is the favored method. The choices of host geological media are salt, basalt, tuff, and granite

Recent advances in cement solidification of radioactive wastes

International Nuclear Information System (INIS)

Vigreux, B.; Jaouen, C.

1987-01-01

Advanced cement solidification processes and systems have been developed by SGN to meet changing requirements in radioactive waste processing and packaging and to avoid the difficulties often encountered in waste concreting on an industrial scale. SGN applies a strict development methodology to ensure integration of the most recent information on chemical behavior of solidified wastes plus compliance with the precise needs of waste producers and evolving regulatory requirements concerning waste package storage and disposal. Based on a hierarchical definition of objectives, this methodology was implemented following an overall study on radwaste concreting performed in 1983 and 1984 for Electricite de France (EdF), France's national electric power utility. It ensures that industrial and regulatory factors are fully considered from the start of development work. It also constrains development in the direction of true process optimization and guarantees compliance with defined objectives. The methodology has helped SGN develop concreting processes adapted to various types of radioactive waste. The most widely employed processes are first briefly described in this paper. It then presents continuous and batch systems using these processes, focusing on technological features chosen at a very early stage in development

The selection, licensing, and operation of a low-level radioactive waste incinerator

International Nuclear Information System (INIS)

Arrowsmith, H.W.; Dalton, D.

1990-01-01

The Scientific Ecology Group has just completed the selection, procurement, licensing, and start-up of a low-level radioactive waste incinerator. This incinerator is the only commercial radioactive waste incinerator in the US and was licensed by the Environmental Protection Agency, the State of Tennessee, the City of Oak Ridge, and the Tennessee Valley Authority. This incinerator has a thermal capacity of 13,000,000 BTUs and can burn approximately 1,000 pounds per hour of typical radioactive waste. Waste to be incinerated is sorted in a new waste sorting system at the SEG facility. The sorting is essential to assure that the incinerator will not be damaged by any unexpected waste and to maintain the purity of the incinerator off-gas. The volume reduction expected for typical waste is approximately 100:1. After burning, the incinerator ash is compacted or vitrified before shipment to burial sites

Method and apparatus for solidifying radioactive waste

International Nuclear Information System (INIS)

Kadota, Hiroko; Kikuchi, Makoto; Tsuchiya, Hiroyuki; Tamada, Shin.

1989-01-01

The present invention concerns a method of solidifying radioactive wastes that generate heat with water curing solidifying material and the object there of is suppress the effect of heat generation of the wastes given on the solidification material. That is, it is a feature of the invention to inject water content contained in the water curable solidification material in the form of ice into the wastes. Thus, since the water content in the water curable solidification material is ice, the solidification products can be obtained by way of the following three steps: (1) ice is dissolved into water, (2) solid content of the solidification material is dissolved into water, and(3) curing reaction of the solidification material is started. Acccordingly, since the heat generated from the wastes contributes as heat of reaction when ice is dissolved into water till the solidification material has been completely filled, promotion for the curing reaction causing problems so far can be suppressed to enable easy filling. Then, after the completion of the filling of the solidification material, the heat of the wastes has an effect of promoting the second and the third steps described above to accelerate the curing reaction. (K.M.)

Management of waste contaminated with alpha emitters

International Nuclear Information System (INIS)

Cartier, R.; Durec, J.P.

1993-01-01

Although advances are being made in the deep geological storage concept, it will probably never be possible to dispose of all types and quantities of radioactive waste in geological formations. Permanent storage should therefore only be considered as an option for final waste disposal. We are currently obliged to search for technological solutions which will reduce the quantities of waste to be managed by future generations, and to ensure that such management can be carried out safely without releasing elements detrimental to the environment into the biosphere. This clearly stated determination, combined with an attitude of complete openness, will secure public acceptance of nuclear energy. As a result of the Research and Development work described here, in March 1992 the Valduc Nuclear Research Center decided to build an industrial waste incineration facility. The facility was to have an annual incinerating capacity of 26 tonnes of waste with a mean radioactivity level of 7.5*10 8 Bq/kg (0.02 Ci/kg). Detailed design studies are in progress, procurements have been launched and construction of the building has started. Commercial operation is scheduled for late 1995. 4 refs. 2 figs

The conceptual design of waste repository for radioactive waste from medical, industrial and research facilities containing comparatively high radioactivity

International Nuclear Information System (INIS)

Yamamoto, Masayuki; Hashimoto, Naro

2002-02-01

Advisory Committee on Nuclear Fuel Cycle Backend Policy reported the basic approach to the RI and Institute etc. wastes on March 2002. According to it, radioactive waste form medical, industrial and research facilities should be classified by their radioactivity properties and physical and chemical properties, and should be disposed in the appropriate types of repository with that classification. For the radioactive waste containing comparatively high radioactivity generated from reactors, NSC has established the Concentration limit for disposal. NSC is now discussing about the limit for the radioactive waste from medical, industrial and research facilities containing comparatively high radioactivity. Japan Nuclear Cycle Development Institute (JNC) preliminary studied about the repository for radioactive waste from medical, industrial and research facilities and discussed about the problems for design on H12. This study was started to consider those problems, and to develop the conceptual design of the repository for radioactive waste from medical, industrial and research facilities. Safety assessment for that repository is also performed. The result of this study showed that radioactive waste from medical, industrial and research facilities of high activity should be disposed in the repository that has higher performance of barrier system comparing with the vault type near surface facility. If the conditions of the natural barrier and the engineering barrier are clearer, optimization of the design will be possible. (author)

Waste Determination Equivalency - 12172

Energy Technology Data Exchange (ETDEWEB)

Freeman, Rebecca D. [Savannah River Remediation (United States)

2012-07-01

by the Secretary of Energy in January of 2006 based on proposed processing techniques with the expectation that it could be revised as new processing capabilities became viable. Once signed, however, it became evident that any changes would require lengthy review and another determination signed by the Secretary of Energy. With the maturation of additional salt removal technologies and the extension of the SWPF start-up date, it becomes necessary to define 'equivalency' to the processes laid out in the original determination. For the purposes of SRS, any waste not processed through Interim Salt Processing must be processed through SWPF or an equivalent process, and therefore a clear statement of the requirements for a process to be equivalent to SWPF becomes necessary. (authors)

Near-adult height in male kidney transplant recipients started on growth hormone treatment in late puberty.

Science.gov (United States)

Gil, Silvia; Aziz, Mariana; Adragna, Marta; Monteverde, Marta; Belgorosky, Alicia

2018-01-01

Growth retardation and its impact on adult height is considered to be one of the most common complications in patients with chronic kidney disease (CKD). Treatment with recombinant human growth hormone (rhGH) has been effective in improving growth in kidney transplantation (KTx) patients, but little data are available on adult height in patients who began rhGh treatment in late puberty. Near-adult height was evaluated in 13 KTx patients treated with rhGH [growth hormone group (GHGr); dose 9.33 mg/m 2 per week] for a period of at least 18 months. At initiation of rhGH treatment, testicular volume was >8 ml and serum testosterone was >1 ng/ml compared with the control group (CGr) of ten KTx patients who did not receive rHGH. All subjects were of similar chronological age and bone age and had similar creatinine clearance (CrCl) levels, cumulative corticoid dose, height standard deviation score (SDS), target height SDS, and target height:initial height at the beginning of the study. Near-adult height was significantly greater in the GHGr than in the CGr (-1.8 ± 0.8 vs. -2.9 ± 1.1; p = 0.018). The difference between initial height and near-adult height in the GHGr revealed a significant height gain (initial height -3.1 ± 1.1; near-adult height -1.8 ± 0.8 SDS, respectively; delta 1.2 ± 0.3; p = 0.021). The CrCl level was not significantly different between the GHGr and CGr at either at study initiation or when attaining near-adult height (p = 0.74 and p = 0.23, respectively). Treatment with rhGH was effective in improving adult height in KTx patients who began treatment in late puberty, without any effect on renal function.

Treatment of waste waters with peat moss

Energy Technology Data Exchange (ETDEWEB)

Coupal, B; Lalancette, J M

1976-01-01

Waste waters containing heavy metals such as Hg, Cd, Zn, Cu, Fe, Ni, Cr/sup 6 +/, Cr/sup 3 +/, Ag, Pb, Sb or cyanide, phosphates and organic matters such as oil, detergents and dyes can be treated efficiently after a crude settling by contacting with peat moss. Chromium, as Cr/sup 6 +/, can be eliminated in one step from a starting solution of low turbidity to give effluent containing less than 10 ppb of Cr/sup 6 +/ and less than 40 ppb of Cr/sup 3 +/. The characteristics and performances of a contacting machine of 20,000 gal/day capacity for the treatment of industrial waste waters are reported.

Remediation of the Provisional Storage of Radioactive Waste near Zavratec

International Nuclear Information System (INIS)

Zeleznik, N.; Mele, I.

1998-01-01

In 1996 the remediation of the provisional storage situated near village Zavratec in western part of Slovenia started. In this storage radioactive waste contaminated with radium has been stored for many decades The RAO Agency organized remedial works, in which these activities inventorying and repacking of radioactive waste were carried out. Simultaneously with these activities a detailed programme for covering public relations was prepared and implemented. On the basis of the experimental results and general storage conditions relocation of radioactive waste to the Slovenian central storage was recommended and it is planned to be concluded by the end of 1998. In this paper main remedial activities in the provisional storage of radioactive waste near Zavratec are presented. An important and most challenging part of these activities represent PR activities. (author)

Evaluation of a Peer-Led, Low-Intensity Physical Activity Program for Older Adults

Science.gov (United States)

Werner, Danilea; Teufel, James; Brown, Stephen L.

2014-01-01

Background: Physical inactivity is a primary contributor to decreasing functional physical fitness and increasing chronic disease in older adults. Purpose: This study assessed the health-related benefits of ExerStart for Lay Leaders, a 20-week, community based, peer-led, low-impact exercise program for older adults. ExerStart focuses on aerobic…

UTILIZATION OF POULTRY, COW AND KITCHEN WASTES FOR BIOGAS PRODUCTION: A COMPARATIVE ANALYSIS

Directory of Open Access Journals (Sweden)

K. Animasahun

2007-09-01

Full Text Available The amount of solid wastes generated in developing countries such as Nigeria has steadily increased over the last two decades as a result of population explosion and continuous growth of industries and agricultural practices. In agriculture, particularly cattle rearing, large quantities of cow wastes are generated, which could be used as biogas inputs to compliment the fuel usage alternative. In addition, a large number of families generate heavy wastes in the kitchen on a daily basis, which could be converted to economic benefits. In this work, a comparative study of biogas production from poultry droppings, cattle dung, and kitchen wastes was conducted under the same operating conditions. 3kg of each waste was mixed with 9L of water and loaded into the three waste reactors. Biogas production was measured for a period of 40 days and at an average temperature of 30.5oC. Biogas production started on the 7th day, and attained maximum value on the 14th days for reactor 1. Production reached its peak on the 14th day with 85´10-3dm3 of gas produced in reactor 2. For reactor 3, biogas production started on the 8th day and production reached a peak value on the 14th day. The average biogas production from poultry droppings, cow dung and kitchen waste was 0.0318dm3/day, 0.0230dm3/day and 0.0143dm3/day, respectively. It is concluded that the wastes can be managed through conversion into biogas, which is a source of income generation for the society.

Preserving the Voices of Adult Educators

Science.gov (United States)

Bogner, Len A.; King, Brett P.

2017-01-01

The Adult Education Interview Series (AEIS) started at the University of Central Oklahoma (UCO) and was inspired by the use of TED talks and other similar videos in online and distance education courses. It is a collaboration between the Adult Education and Safety Science Department and the Center for eLearning and Connected Environments at UCO.…

Determination of the best appropriate management methods for the health-care wastes in Istanbul

International Nuclear Information System (INIS)

Alagoez, Aylin Zeren; Kocasoy, Guenay

2008-01-01

Health-care waste management has been a significant problem in most economically developing countries as it is in Turkey. Most of the time, the main reason for the mismanagement of these wastes is the lack of appropriate legislation and effective control; other reasons are: financial strains and a lack of awareness. Being aware of the significance of the subject, in this paper the management of the health-care wastes in Istanbul, as a Metropolitan City of Turkey, was analyzed to create an integrated health-care waste management system in the city. Within the scope of the study, the existing situation and management practices such as the amount of the health-care wastes generated, segregation procedures, collection, temporary storage and transportation of the wastes within and outside of the institution were examined. Deficiencies, inconsistencies and improper applications were revealed. The existing Turkish Medical Wastes Control Regulation and institutional structure of the health-care waste management body were reviewed. After the evaluation and comparison with the requirements of other national and international organizations, items to be changed/added in the Regulation were identified. At the end of the study, the best management methods for the Istanbul City were determined and started to be applied at the institutions. After this study, the existing Regulation has been changed. The modified Regulation was published in 2005 and implementation has started. It is expected that by the application and implementation of the research outcomes, the management of health-care wastes in Istanbul and then in all over Turkey will be improved. The results obtained can also be used in most economically developing countries where there are similar environmental problems and strict budgets

Start-up phase assessment of a UASB-Septic tank system treating domestic septage

International Nuclear Information System (INIS)

Ali, M.; Al-Saed, R.; Mahmoud, N.

2007-01-01

About 65% of the annual domestic waste water in Palestine is currently collected in cesspits, where inadequate disposal might cause cumulative public health risks and annual environmental degradation. This research presents the preliminary results for the start-up period of a pilot-scale UASB-septic tank system treating domestic septage of Birzet town. Under different operational conditions, the performance of the pretreatment system for the removal of organic matter and nutrients was evaluated. Initial results showed that organic pollutants removal was mainly due to biophysical processes including sedimentation and microbial degradation. During start-up phase, the system attained removal efficiency for COD total of about 80% compared to removal for COD col, and COD dis of 71% and 43% respectively. Similarly, the continuous operation mode demonstrated that the system was quite effective in removing organic pollutants. Operational experience from the initial results revealed that seeding the USAB reactor with activated sludge during the start up period was not practical. Finally, the advantage of USAB-septic tank application appeared to be achievable if adequate system operation and control over a long monitoring period were maintained. (author)

Thermal treatment of municipal waste: An overview

International Nuclear Information System (INIS)

Sivaprasad, K.S.

2010-01-01

Waste generation, like a shadow accompanies all kinds of human activities. For a long time waste was ignored as of no consequence. Nevertheless in recent times the presence of Waste was felt by the adverse impact it began to have on human life. Attention was given to waste disposal. Various methods of disposal were developed. Actually a process of evolution was set in this area. Starting with Dumpsite it developed in to sanitary land fill. Adverse impact was beginning to be seen in leachate contaminating ground water, and long term emission of methane contributing to climate change. This set the thinking to seek other solutions. Waste was begun to be seen as a resource instead of a nuisance to be disposed off. Bio-methanation of waste for recovery of methane rich biogas was developed. The concept of thermal treatment of waste for disposal came in to being in order to reduce volume of disposal as only the ash will be disposed instead of the whole volume of waste when waste is subjected to thermal treatment. However, it was beset with certain pollution problems which needed to be addressed. Suitable pollution abatement systems were developed. In the meantime, with the increase in global population and lifestyle changes across the globe, demand for natural resources went up rapidly resulting in pressure on the finite resources of the earth. Emphasis shifted to recovery of value from waste while disposing. Recovery of Recyclables, and energy came in to focus. RDF technology was developed facilitating this making it possible to recover recyclables like plastics, metals etc besides generating the prepared fuel RDF for energy recovery. (Author)

Process performance and modelling of anaerobic digestion using source-sorted organic household waste

DEFF Research Database (Denmark)

Khoshnevisan, Benyamin; Tsapekos, Panagiotis; Alvarado-Morales, Merlin

2018-01-01

Three distinctive start-up strategies of biogas reactors fed with source-sorted organic fraction of municipal solid waste were investigated to reveal the most reliable procedure for rapid process stabilization. Moreover, the experimental results were compared with mathematical modeling outputs....... The combination of both experimental and modelling/simulation succeeded in optimizing the start-up process for anaerobic digestion of biopulp under mesophilic conditions....

High density polyethylene (HDPE-2) and polystyrene (PS-6) waste plastic mixture turns into valuable fuel energy

Energy Technology Data Exchange (ETDEWEB)

Sarker, Moinuddin; Rashid, Mohammad Mamunor; Rahman, Md. Sadikur; Molla, Mohammed [Department of Research and Development, Natural State Research Inc, Stamford, (United States)

2011-07-01

Disposal of waste plastic is a serious concern in USA. Waste plastic generated from different cities and towns is a part of municipal solid waste. It is a matter of concern that disposal of waste plastic is causing many problems such as leaching impact on land and ground water, choking of drains, making land infertile, indiscriminate burning causes environmental hazards etc. Waste plastics being nonbiodegradable it can remain as a long period of landfill. Over 48 million tons of synthetic polymer material is produced in the United States every year. Plastic are made from limited resources such as petroleum. When waste plastic come in contact with light and starts photo degrading, it starts releasing harmful such as carbon, chlorine and sulfur causing the soil around them to decay, contributing many complications for cultivation. Waste plastics also end up in the ocean, where it becomes small particles due to the reaction caused by the sun ray and salt from the ocean. Million of ocean habitants die from consuming these small plastic particles when they mistake them for food. To solve this problem countries are resorting to dumping the waste plastics, which requires a lot of effort and money yet they are only able to recycle a fraction of waste plastics. This developed a new technology which will remove these waste plastics form landfill and ocean and convert them into useful liquid fuels. The fuels show high potential for commercialization due to the fact, its influence to the environment. Keywords: waste plastics, fuel, energy, polystyrene, high density polyethylene, thermal, environmental.

Hanford ferrocyanide waste chemistry and reactivity preliminary catalyst and initiator screening studies

International Nuclear Information System (INIS)

Scheele, R.D.; Bryan, S.A.; Johnston, J.W.; Tingey, J.M.; Burger, L.L.; Hallen, R.T.

1992-05-01

During the 1950s, ferrocyanide was used to scavenge radiocesium from aqueous nitrate-containing Hanford wastes. During the production of defense materials and while these wastes were stored in high-level waste tanks at the Hanford Site, some of these wastes were likely mixed with other waste constituents and materials. Recently, Pacific Northwest Laboratory (PNL) was commissioned by Westinghouse Hanford Company (WHC) to investigate the chemical reactivity of these ferrocyanide-bearing wastes. Because of known or potential thermal reactivity hazards associated with ferrocyanide- and nitrate-bearing wastes, and because of the potential for different materials to act as catalysts or initiators of the reactions about which there is concern, we at PNL have begun investigating the effects of the other potential waste constituents. This report presents the results of a preliminary screening study to identify classes of materials that might be in the Hanford high-level waste tanks and that could accelerate or reduce the starting temperature of the reaction(s) of concern. We plan to use the resulted of this study to determine which materials or class of materials merit additional research

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.

Greenhouse gas accounting and waste management.

Science.gov (United States)

Gentil, Emmanuel; Christensen, Thomas H; Aoustin, Emmanuelle

2009-11-01

Accounting of emissions of greenhouse gas (GHG) is a major focus within waste management. This paper analyses and compares the four main types of GHG accounting in waste management including their special features and approaches: the national accounting, with reference to the Intergovernmental Panel on Climate Change (IPCC), the corporate level, as part of the annual reporting on environmental issues and social responsibility, life-cycle assessment (LCA), as an environmental basis for assessing waste management systems and technologies, and finally, the carbon trading methodology, and more specifically, the clean development mechanism (CDM) methodology, introduced to support cost-effective reduction in GHG emissions. These types of GHG accounting, in principle, have a common starting point in technical data on GHG emissions from specific waste technologies and plants, but the limited availability of data and, moreover, the different scopes of the accounting lead to many ways of quantifying emissions and producing the accounts. The importance of transparency in GHG accounting is emphasised regarding waste type, waste composition, time period considered, GHGs included, global warming potential (GWP) assigned to the GHGs, counting of biogenic carbon dioxide, choice of system boundaries, interactions with the energy system, and generic emissions factors. In order to enhance transparency and consistency, a format called the upstream-operating-downstream framework (UOD) is proposed for reporting basic technology-related data regarding GHG issues including a clear distinction between direct emissions from waste management technologies, indirect upstream (use of energy and materials) and indirect downstream (production of energy, delivery of secondary materials) activities.

Slovak Nuclear Regulatory Body Position in the Transport of Radioactive Waste

International Nuclear Information System (INIS)

Homola, J.

2003-01-01

This paper describes safety requirements for transport of radioactive waste in Slovakia and the role of regulatory body in the transport licensing and assessment processes. Importance of radioactive waste shipments have been increased since 1999 by starting of NPP A-1 decommissioning and operation of near surface disposal facility. Also some information from history of shipment as well as future activities are given. Legal basis for radioactive waste transport is resulting from IAEA recommendations in this area. Different types of transport equipment were approved by regulatory body for both liquid and solid waste and transportation permits were issued to their shipment. Regulatory body attention during evaluation of transport safety is focused mainly on ability of individual packages to withstand different transport conditions and on safety analyses performed for transport equipment for liquid waste with high frequency of shipments. During past three years no event was occurred in connection with radioactive waste transport in Slovakia

Public concerns and behaviours towards solid waste management in Italy.

Science.gov (United States)

Sessa, Alessandra; Di Giuseppe, Gabriella; Marinelli, Paolo; Angelillo, Italo F

2010-12-01

A self-administered questionnaire investigated knowledge, perceptions of the risks to health associated with solid waste management, and practices about waste management in a random sample of 1181 adults in Italy. Perceived risk of developing cancer due to solid waste burning was significantly higher in females, younger, with an educational level lower than university and who believed that improper waste management is linked to cancer. Respondents who had visited a physician at least once in the last year for fear of contracting a disease due to the non-correct waste management had an educational level lower than university, have modified dietary habits for fear of contracting disease due to improper waste management, believe that improper waste management is linked to allergies, perceive a higher risk of contracting infectious disease due to improper waste management and have participated in education/information activities on waste management. Those who more frequently perform with regularity differentiate household waste collection had a university educational level, perceived a higher risk of developing cancer due to solid waste burning, had received information about waste collection and did not need information about waste management. Educational programmes are needed to modify public concern about adverse health effects of domestic waste.

An Overview of Food Loss and Waste: why does it Matter?

Science.gov (United States)

Ghosh, Purabi R.; Sharma, Shashi B.; Haigh, Yvonne T.; Evers, A. L. Barbara; Ho, Goen

2015-10-01

This paper provides an overview of food waste in the context of food security, resources management and environment health. It compares approaches taken by various governments, community groups, civil societies and private sector organisations to reduce food waste in the developed and developing countries. What constitutes ‘food waste’ is not as simple as it may appear due to diverse food waste measurement protocols and different data documentation methods used worldwide. There is a need to improve food waste data collection methods and implementation of effective strategies, policies and actions to reduce food waste. Global initiatives are urgently needed to: enhance awareness of the value of food; encourage countries to develop policies that motivate community and businesses to reduce food waste; encourage and provide assistance to needy countries for improving markets, transport and storage infrastructure to minimise food waste across the value chain; and, develop incentives that encourage businesses to donate food. In some countries, particularly in Europe, initiatives on food waste management have started to gain momentum. Food waste is a global problem and it needs urgent attention and integrated actions of stakeholders across the food value chain to develop global solutions for the present and future generations.

Adult Bed-Wetting: A Concern?

Science.gov (United States)

Adult bed-wetting: A concern? My 24-year-old husband has started to wet the bed at ... of Privacy Practices Notice of Nondiscrimination Manage Cookies Advertising Mayo Clinic is a not-for-profit organization ...

ETHEL's systems and facilities for safe management of tritiated wastes

International Nuclear Information System (INIS)

Mannone, F.; Dworschak, H.; Vassallo, G.

1992-01-01

The European Tritium Handling Experimental Laboratory (ETHEL) is a new tritium facility at the Commission of the European Community's Joint Research Centre, Ispra Site. The laboratory, destined to handle multigram amounts of tritium for safety related R and D purposes, is foreseen to start radioactive operations in late 1992. The general operation and maintenance of laboratory systems and future experiments will generate tritiated wastes in gaseous, liquid and solid forms. The management of such wastes under safe working conditions is a stringent laboratory requirement aimed at minimizing the risk of unacceptable tritium exposures to workers and the general public. This paper describes the main systems and facilities installed in ETHEL for the safe management of tritiated wastes

Development and problems of radioactive waste management infrastructure in Estonia

International Nuclear Information System (INIS)

Putnik, H.; Realo, E.

2001-01-01

Estonia is one of a few countries where the establishment of radiation protection and radioactive waste management infrastructure started only recently, soon after regaining independence in the beginning of 1990's. Both legislative and regulatory infrastructure had to be built from scratch, in parallel with the beginning of urgent activities and practices to manage waste streams inherited from the past. Despite significant deficiency of local expertise and specialists in the field, the main objectives of the establishment were set up: to enforce national legislation basing on contemporary international principles, criteria, requirements and to implement structures and procedures for an efficient regulation of radiation safety issues, including practices involving radioactive waste management and decommissioning

Report on site-independent environmental impacts of radioactive waste storage and management

International Nuclear Information System (INIS)

1985-10-01

The organisation responsible for radioactive wastes in the Netherlands is COVRA: Centrale Organisatie Voor Radioactief Afval. It deals especially with storage and management of these wastes. For that purpose, COVRA will build a waste managing and storage facility at a central site in the Netherlands. In this report, environmental impacts of these activities are studied, that are independent of the location. The report is readable and useful for a broad audience. In the main report, the general features are outlined starting from figures and tables on environmental effects. In a separate volume, detailed numerical data are presented. (G.J.P.)

Public perception on nuclear energy and radioactive waste - The second opinion poll

International Nuclear Information System (INIS)

Diaconu, Stela; Covreag Ilinca

2009-01-01

In 2008 ANDRAD started the second national opinion poll which had the purpose to identify the support of Romanian citizen for energy production by nuclear power stations, which is perceived as a less expensive energy, that could reduces the oil dependence of our country. The questionnaire consisted in 22 questions aiming to assess: the level of information about radioactive waste, the actual knowledge about radioactive waste management, the support and the opinion on nuclear energy, the public attitude regarding radioactive waste disposal, the trust in information sources and the public involvement in the decision-making process. (authors)

Solidification of ash from incineration of low-level radioactive waste

International Nuclear Information System (INIS)

Roberson, W.A.; Albenesius, E.L.; Becker, G.W.

1983-01-01

The safe disposal of both high-level and low-level radioactive waste is a problem of increasing national attention. A full-scale incineration and solidification process to dispose of suspect-level and low-level beta-gamma contaminated combustible waste is being demonstrated at the Savannah River Plant (SRP) and Savannah River Laboratory (SRL). The stabilized wasteform generated by the process will meet or exceed all future anticipated requirements for improved disposal of low-level waste. The incineration process has been evaluated at SRL using nonradioactive wastes, and is presently being started up in SRP to process suspect-level radioactive wastes. A cement solidification process for incineration products is currently being evaluated by SRL, and will be included with the incineration process in SRP during the winter of 1984. The GEM alumnus author conducted research in a related disposal solidification program during the GEM-sponsored summer internship, and upon completion of the Masters program, received full-time responsibility for developing the incineration products solidification process

Long-term management of wastes resulting from dismantling operations. Storing the very low-level activity wastes at Morvilliers

International Nuclear Information System (INIS)

Duret, F.; Dutzer, M.; Beranger, V.; Lecoq, P.

2003-01-01

Extension of dismantling operations in France in the years to come poses the question of availability of long-term waste facility. Large amount of such wastes will be produced after progressive shutdown of the 58 pressurized water reactors now in operation, not before 2010. However, France is already confronted with dismantling of 9 power reactors (6 of which of gas cooled graphite type), the first reprocessing plant at Marcoule, as well as, dismantling of other installations, for instance the CEA reactors or laboratories. The systems of processing the dismantling waste are not different from those used for wastes resulting from nuclear operations. For the high-level or long-term intermediate level activity disposal the debates must start by 2006, as based on the results of the research conducted according to different provisions of the December 30, 1991 law. These wastes represent however small amounts from the dismantling (around 2000 t for the 9 reactors at shutdown) and they will be stored until a decision will be made. A specific storing system should be implemented by 2008-2010 for the graphite wastes (around 23,000 t) which contain significant amount of long-lived radioelements, although their gross activity is low. But the most significant amount will come from low-level or intermediate-level of short lifetime or from wastes of very low activity. The first category is stored at Storage Center at Aube (CSA), its capacity being of 1,000,000 m 3 of drums. The total volume stored by the end of 2002 amounted 136,500 m 3 with an annual delivering of 12-15,000 m 3 at design rate of 30,000 m 3 /y. This center will be able to absorb the flux increase resulting from dismantling of the decommissioned nuclear installations (around 50,000 t from the dismantling of the 9 power reactor). The Center at Aube can be also adapted for storing wastes of large sizes as for instance the lid of the reactor vessel. According to the French regulation, the wastes produced within a

Hanford Waste Vitrification Project overview and status

International Nuclear Information System (INIS)

Swenson, L.D.; Smets, J.L.

1993-01-01

The Hanford Waste Vitrification Project (HWVP) is being constructed at the US DOE's Hanford Site in Richland, WA. Engineering and design are being accomplished by Fluor Daniel Inc. in Irvine, CA. Technical input is furnished by Westinghouse Hanford Co. and construction management services by UE ampersand C-Catalytic Inc. The HWVP will immobilize high level nuclear waste in a glass matrix for eventual disposal in the federal repository. The HWVP consists of several structures, the major ones being the Vitrification Building, the Canister Storage Building, fan house, sand filter, waste hold tank, pump house, and administration and construction facilities. Construction started in April 1992 with the clearing and grubbing activities that prepared the site for fencing and construction preparation. Several design packages have been released for procurement activities. The most significant package release is for the Canister Storage Building, which will be the first major structure to be constructed

Mobile polishing system of feedwater at start-up feedback from the implementation and future prospects

International Nuclear Information System (INIS)

Faure, Celine; Eade, Kevin; Fontan, Guillaume

2012-09-01

The reduction of the quantity of Steam Generator (SG) metallic oxides deposits, and maintaining a good chemical composition of the secondary side of SG tubes are some of the main objectives being looked at, in order to reduce the risk of SG corrosion, regardless of the alloy used, right from the start-up phase. For all types of outage, obtaining and maintaining sufficient chemical cleanliness at the start-up requires treatment of the water. The treatments are notably: - Water movements using the purge / make-up water method until the chemical criteria have been met. This method can be long and generate large volumes of discharge. - Using suitable resins to remove pollutants from the water. The advantage of this method is that it is selective. - Filtration, allowing for the removal of any insoluble agent. In order to optimise the start-up process, Gravelines and Blayais Nuclear Power Plants (NPPs) put trials in place towards the end of the 1980s. These trials lead to a water supply treatment installation (mobile polishing system- in French Systeme Mobile d'Epuration, SME) being put in place for the start-up phase, made up of an up-stream filter, a mixed-bed resin pollutant trap and a down-stream filter to prevent losing the fines into the feedwater. At the same time, the manifestation of cracking on the secondary side of the steam generator tubes lead EDF to roll out a water treatment for the feedwater dedicated to the start-up. The choice was made not to install a condensate polishing plant, in order to limit notably the pollution risks (resin leaks or waste from the regeneration in the backwater) following difficulties during regeneration. The positive results from the first trials validated for EDF the choice to give priority to the roll-out of the SME to the NPPs judged to be most critical due to the SG material. The SME, installed on a mobile base, can be used on different units at the same station; this reduced the investment and maintenance costs, and

Pairing the Adult Learner and Boutique Wineries

Science.gov (United States)

Holyoke, Laura; Heath-Simpson, Delta

2013-01-01

This study explored connections between adult learners and their experiences in the context of small boutique wineries operating in the start-up phase of the organizational life cycle. The research objective was to gain insight regarding the pairing of adult learners with the entering of a specialty industry. Fourteen individuals from four…

Application of Epoxy Based Coating Instacote on Waste Tank Tops

International Nuclear Information System (INIS)

Pike, J.A.

1998-01-01

This evaluation examines the compatibility of coating Instacote with existing High-Level Waste facilities and safety practices. No significant incompatibilities are identified. The following actions need to be completed as indicated when applying Instacote on waste tank tops:(1) Prior to application in ITP facilities, the final product should be tested for chemical resistance to sodium tetraphenylborate solutions or sodium titanate slurries.(2) Any waste contaminated with Part A or B that can not be removed by the vendor such as for radiological contamination, HLW must hold the waste until HLW completes a formal assessment of the waste, disposal criteria, and impact.(3) Prior to the start of any application of the coating, each riser needs to be evaluated for masking and masking applied if needed.(4) At the conclusion of an application actual total weight of material applied to a waste tank needs to documented and sent to the tank top loading files for reference purposes.(5) Verify that the final product contains less than 250 ppm chloride

Community mobilization and household level waste management for dengue vector control in Gampaha district of Sri Lanka; an intervention study.

Science.gov (United States)

Abeyewickreme, W; Wickremasinghe, A R; Karunatilake, K; Sommerfeld, J; Axel, Kroeger

2012-12-01

Waste management through community mobilization to reduce breeding places at household level could be an effective and sustainable dengue vector control strategy in areas where vector breeding takes place in small discarded water containers. The objective of this study was to assess the validity of this assumption. An intervention study was conducted from February 2009 to February 2010 in the populous Gampaha District of Sri Lanka. Eight neighborhoods (clusters) with roughly 200 houses each were selected randomly from high and low dengue endemic areas; 4 of them were allocated to the intervention arm (2 in the high and 2 in the low endemicity areas) and in the same way 4 clusters to the control arm. A baseline household survey was conducted and entomological and sociological surveys were carried out simultaneously at baseline, at 3 months, at 9 months and at 15 months after the start of the intervention. The intervention programme in the treatment clusters consisted of building partnerships of local stakeholders, waste management at household level, the promotion of composting biodegradable household waste, raising awareness on the importance of solid waste management in dengue control and improving garbage collection with the assistance of local government authorities. The intervention and control clusters were very similar and there were no significant differences in pupal and larval indices of Aedes mosquitoes. The establishment of partnerships among local authorities was well accepted and sustainable; the involvement of communities and households was successful. Waste management with the elimination of the most productive water container types (bowls, tins, bottles) led to a significant reduction of pupal indices as a proxy for adult vector densities. The coordination of local authorities along with increased household responsibility for targeted vector interventions (in our case solid waste management due to the type of preferred vector breeding places) is

Later Start, Longer Sleep: Implications of Middle School Start Times

Science.gov (United States)

Temkin, Deborah A.; Princiotta, Daniel; Ryberg, Renee; Lewin, Daniel S.

2018-01-01

Background: Although adolescents generally get less than the recommended 9 hours of sleep per night, research and effort to delay school start times have generally focused on high schools. This study assesses the relation between school start times and sleep in middle school students while accounting for potentially confounding demographic…

Radioactive waste management: review on clearance levels and acceptance criteria legislation, requirements and standards.

Science.gov (United States)

Maringer, F J; Suráň, J; Kovář, P; Chauvenet, B; Peyres, V; García-Toraño, E; Cozzella, M L; De Felice, P; Vodenik, B; Hult, M; Rosengård, U; Merimaa, M; Szücs, L; Jeffery, C; Dean, J C J; Tymiński, Z; Arnold, D; Hinca, R; Mirescu, G

2013-11-01

In 2011 the joint research project Metrology for Radioactive Waste Management (MetroRWM)(1) of the European Metrology Research Programme (EMRP) started with a total duration of three years. Within this project, new metrological resources for the assessment of radioactive waste, including their calibration with new reference materials traceable to national standards will be developed. This paper gives a review on national, European and international strategies as basis for science-based metrological requirements in clearance and acceptance of radioactive waste. © 2013 Elsevier Ltd. All rights reserved.

The Italian START-Register on Anticoagulation with Focus on Atrial Fibrillation

Science.gov (United States)

2015-01-01

START-Register – Survey on anTicoagulated pAtients RegisTer – is an independent, inception-cohort, observational, collaborative database aimed at recording prospectively the clinical history of adult patients starting anticoagulant treatment for any reason and using whatever drug. In this article we present the START-Register and give cross section baseline data focusing on non valvular atrial fibrillation (NVAF). Participants are asked to insert prospectively consecutive patients recorded as electronic file on the web-site of the registry. Required data are: demographic and clinical characteristics of patients, associated risk factors for stroke and bleeding, laboratory routine data, clinical indication for treatment, expected therapeutic range (in cases of treatment with vitamin K antagonists -VKAs). The follow-up is carried out to record: quality of treatment (for patients on VKAs), bleeding complications, thrombotic events, and the onset of any type of associated disease. To date 5252 patients have been enrolled; 97.6% were on VKAs because direct oral anticoagulants (DOAC) have been available in Italy only recently. The median age was 74 years [interquartile range (IQR) 64-80]; males 53.7%. This analysis is focused on the 3209 (61.1%) NVAF patients. Mean CHADS2 score was 2.1±1.1, CHADSVASc score was 3.1±1.3;median age was 76 years (IQR 70-81); 168 patients (5.3%) had severe renal failure [Creatinine clearance (CrCl) START-Register data shows that two-third of patients who started chronic anticoagulant treatment had NVAF, one-third of them was > 80 years with high prevalence of renal failure. PMID:26001109

An analytical one-dimensional model for predicting waste package performance

International Nuclear Information System (INIS)

Relyea, J.F.; Wood, M.I.

1984-01-01

A method for allocating waste package performance requirements among waste package components with regard to radionuclide isolation has been developed. Modification or change in this approach can be expected as the understanding of radionuclide behavior in the waste package improves. Thus, the performance requirements derived in this document are preliminary and subject to change. However, this kind of analysis is a useful starting point. It has also proved useful for identifying a small group of radionuclides which should be emphasized in a laboratory experimental program designed to characterize the behavior of specific radionuclides in the waste package environment. A simple one-dimensional, two media transport model has been derived and used to calculate radionuclide transport from the waste form-packing material interface of the waste package into the host rock. Cumulative release over 10,000 years, maximum yearly releases and release rates at the packing material-host rock interface were evaluated on a radionuclide-by radionuclide basis. The major parameters controlling radionuclide release were found to be: radionuclide solubility, porosity of the rock, isotopic ratio of the radionuclide and surface area of the waste form-packing material interface. 15 refs., 2 figs., 16 tabs

Characteristics and survival of young adults who started renal replacement therapy during childhood

NARCIS (Netherlands)

Kramer, Anneke; Stel, Vianda S.; Tizard, Jane; Verrina, Enrico; Rönnholm, Kai; Pálsson, Runólfur; Maxwell, Heather; Jager, Kitty J.

2009-01-01

BACKGROUND: Little is known about the group of children on renal replacement therapy (RRT) who reach the age of 18 years and are transferred from paediatric to adult nephrology services. The aim of this study was to describe patient demographics, primary renal diseases, treatment history and

Radioactive Waste Disposal Pilot Plant concept for a New Mexico site

International Nuclear Information System (INIS)

Weart, W.D.

1976-01-01

Twenty years of investigation have shown that disposal of nuclear wastes in deep salt formations is the surest means of isolating these wastes from the biosphere for the extremely long period of time required. A large scale demonstration of this capability will soon be provided by a Radioactive Waste Disposal Pilot Plant (RWDPP) to be developed in southeastern New Mexico. Initially, the pilot plant will accept only ERDA generated waste; high level waste from the commercial power reactor fuel cycle will eventually be accommodated in the pilot plant and the initial RWDPP design will be compatible with this waste form. Selection of a specific site and salt horizon will be completed in June 1976. Conceptual design of the RWDPP and assessment of its environmental impact will be completed by June 1977. Construction is expected to start in 1978 with first waste accepted in 1982. The present concept develops disposal areas for all nuclear waste types in a single salt horizon about 800 meters deep. This single level can accommodate all low level and high level waste generated in the United States through the year 2010. A major constraint on the RWDPP design is the ERDA requirement that all waste be ''readily'' retrievable during the duration of pilot plant operation

Characterization the radioactive waste with a view to its possible declassification

International Nuclear Information System (INIS)

Domenech, Aidee; Cornejo Diaz, Nestor

1998-01-01

In the present work the currents are characterized the waste that take place in the medicine and the investigation and the possibilities are valued for to declassify some at they starting from the estimate give levels dispensation derived for different radionuclides

Evaluation of the Even Start--Padres y Progreso Program in the Houston Independent School District.

Science.gov (United States)

Stevens, Carla J.; And Others

The Even Start-Padres y Progreso program is a nationally funded program designed to prepare young children to enter school by not only offering early childhood education, but also assisting their families with adult literacy and English as a Second Language (ESL), parenting-skills training, and employment-skills training. An evaluation of the…

Evaluation of the Fourth and Final Year of the Even Start--Padres y Progreso Program.

Science.gov (United States)

Stevens, Carla J.; And Others

The Even Start--Padres y Progreso program was a nationally funded program in Houston (Texas) designed to prepare young children to enter school not only by offering early childhood education, but also assisting their families with adult literacy/English as a second language, parenting skills training, and employment skills training. The program…

Metal waste forms from the electrometallurgical treatment of spent nuclear fuel

International Nuclear Information System (INIS)

Abraham, D.P.; McDeavitt, S.M.; Park, J.

1996-01-01

Stainless steel-zirconium alloys are being developed for the disposal of radioactive metal isotopes isolated using an electrometallurgical treatment technique to treat spent nuclear fuel. The nominal waste forms are stainless steel-15 wt% zirconium alloy and zirconium-8 wt% stainless steel alloy. These alloys are generated in yttria crucibles by melting the starting materials at 1,600 C under an argon atmosphere. This paper discusses the microstructures, corrosion and mechanical test results, and thermophysical properties of the metal waste form alloys

Anaerobic digestion of cellulosic wastes: laboratory tests

International Nuclear Information System (INIS)

Lee, D.D.; Donaldson, T.L.

1984-11-01

Anaerobic digestion is a potentially attractive technology for volume reduction of cellulosic wastes. A substantial fraction of the waste is converted to off-gas and a relatively small volume of biologically stabilized sludge is produced. Process development work is underway using a 75-L digester to verify rates and conversions obtained at the bench scale, to develop start-up and operating procedures, and to generate effluent for characterization and disposal studies. Three runs using batch and batch-fed conditions have been made lasting 36, 90, and over 200 days. Solids solubilization and gas production rates and total solids destruction have met or exceeded the target values of 0.6 g cellulose per L of reactor per day, 0.5 L off-gas per L of reactor per day, and 80% destruction of solids, respectively. Successful start-up procedures have been developed, and preliminary effluent characterization and disposal studies have been done. A simple dynamic process model has been constructed to aid in further process development and for use in process monitoring and control of a large-scale digester. 10 references, 17 figures, 4 tables

Young adults with very low birth weight: leaving the parental home and sexual relationships--Helsinki Study of Very Low Birth Weight Adults.

Science.gov (United States)

Kajantie, Eero; Hovi, Petteri; Räikkönen, Katri; Pesonen, Anu-Katriina; Heinonen, Kati; Järvenpää, Anna-Liisa; Eriksson, Johan G; Strang-Karlsson, Sonja; Andersson, Sture

2008-07-01

Although most children and adults who are born very preterm live healthy lives, they have, on average, lower cognitive scores, more internalizing behaviors, and deficits in social skills. This could well affect their transition to adulthood. We studied the tempo of first leaving the parental home and starting cohabitation with an intimate partner and sexual experience of young adults with very low birth weight (Adults, 162 very low birth weight individuals and 188 individuals who were born at term (mean age: 22.3 years [range: 18.5-27.1]) and did not have any major disability filled out a questionnaire. For analysis of their ages at events which had not occurred in all subjects, we used survival analysis (Cox regression), adjusted for gender, current height, parents' ages at the birth, maternal smoking during pregnancy, parental educational attainment, number of siblings, and parental divorce/death. During their late teens and early adulthood, these very low birth weight adults were less likely to leave the parental home and to start cohabiting with an intimate partner. In gender-stratified analyses, these hazard ratios were similar between genders, but the latter was statistically significant for women only. These very low birth weight adults were also less likely to experience sexual intercourse. This relationship was statistically significant for women but not for men; however, very low birth weight women and men both reported a smaller lifetime number of sex partners than did control subjects. Healthy young adults with very low birth weight show a delay in leaving the parental home and starting sexual activity and partnerships.

Municipal solid waste management in Tehran: Changes during the last 5 years.

Science.gov (United States)

Malmir, Tahereh; Tojo, Yasumasa

2016-05-01

The situation of waste management in Tehran was a typical example of it in developing countries. The amount of municipal solid waste has been increasing and the city has depended on landfill for municipal solid waste management. However, in recent years, various measures have been taken by the city, such as collecting recyclables at the source and increasing the capacity of waste-processing facilities. As a result, significant changes in the waste stream are starting to occur. This study investigated the nature of, and reasons for, the marked changes in the waste stream from 2008 to 2012 by analysing the municipal solid waste statistics published by the Tehran Waste Management Organization in 2013 and survey data on the physical composition of the municipal solid waste. The following trends were identified: Although the generation of municipal solid waste increased by 10% during the 5-year period, the amount of waste directly disposed of to landfill halved and resource recovery almost doubled. An increase in the capacity of a waste-processing facility contributed significantly to these changes. The biodegradable fraction going to landfill was estimated by using the quantity and the composition of each input to the landfill. The estimated result in 2012 decreased to 49% of its value in 2008. © The Author(s) 2016.

Small mammal populations at hazardous waste disposal sites near Houston, Texas, USA

Science.gov (United States)

Robbins, C.S.

1990-01-01

Small mammals were trapped, tagged and recaptured in 0?45 ha plots at six hazardous industrial waste disposal sites to determine if populations, body mass and age structures were different from paired control site plots. Low numbers of six species of small mammals were captured on industrial waste sites or control sites. Only populations of hispid cotton rats at industrial waste sites and control sites were large enough for comparisons. Overall population numbers, age structure, and body mass of adult male and female cotton rats were similar at industrial waste sites and control sites. Populations of small mammals (particularly hispid cotton rats) may not suffice as indicators of environments with hazardous industrial waste contamination.

"Starting from Ground Zero:" Constraints and Experiences of Adult Women Returning to College

Science.gov (United States)

Deutsch, Nancy L.; Schmertz, Barbara

2011-01-01

Women adult students face particular constraints when pursuing degrees. This paper uses focus group data to explore the educational pathways, barriers, and supports of women students. Women's educations are shaped by personal and structural gendered forces, including family, economic, and workplace issues. Women report conflict over short-term…

A Novel Method of Biological Start-up in Arak Activated Sludge Wastewater Treatment Plant

Directory of Open Access Journals (Sweden)

Abdolreza Khalili

2015-01-01

Full Text Available Startup is one of the most important stages in the operation of a wastewater treatment plant (WWTP. In this paper, a novel method is presented for the startup of Arak Activated Sludge WWTP, which is shown to contain more advantages than other common methods. In this method, a portion of the inflow is initially allowed to enter gradually into an aeration basin prior to seeding. Under these conditions, less seeding is required due to the low flow of the influent and the low volume of the aeration basin. Once MLSS in the basin reaches the desired level, the rest of the system comes into operation and the sludge developed in the system is used for further seeding. In the case of the WWPT in Arak, it took about 2 months for the total MLSS to be developed and wasting the sludge to start because of the cold weather conditions in the region. The wasted sludge was controlled by the F/M ratio at a constant sludge age. During the start-up, the MLSS increase exhibited a linear trend and the low loading allowed for the variation in influent contaminants to be controlled. The effluent contaminants were below the standard levels recommended by the Environment Protection Organization. BOD5 and COD removals increased from 40% and 60% to 90% and TSS removal increased from 70% to 96%. Lower loading levels, better process control, and lower sludge processing costs are the benefits of this system

76 FR 37174 - Capital Investment Program-New Starts and Small Starts Program Funds

Science.gov (United States)

2011-06-24

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Capital Investment Program--New Starts... apportionment of the FY 2011 Capital Investment (New Starts and Small Starts) program funds. The funds will be... FY 2011, $1,596,800,000 was appropriated for the Capital Investments Grant Account, which includes...

Who owns urban waste? Appropriation conflicts in emerging countries.

Science.gov (United States)

Cavé, Jérémie

2014-09-01

Managing solid waste in developing cities is not an easy task and many public policies have failed to bring the expected results. It is here argued that comprehending the solid waste handling in the South implies reconsidering the proper definition of waste. Where does the product end and where does rubbish begin? The answer to this question is far from being obvious. Solid waste appears as a blurred concept. Such a thorny issue is all the more relevant today, as municipal solid waste management approaches in the developing world are being reformulated: dumping sites are banned, sanitary landfills are imposed, and separate collection is being introduced. The current sector transformations are here analysed through a novel theoretical analysis combined with an original qualitative and quantitative empirical work. Through two case-studies of one-million inhabitant cities from emerging countries, it is shown that if appropriation conflicts arise that is because the urban solid waste deposit in Southern countries can be defined as an impure public good. This issue does not only involve private service operators and informal wastepickers; several other actors covet the urban solid waste deposit's cream, that is, recyclable items. In emerging countries, huge industrial groups are starting to target domestic recyclable waste as an alternative for raw materials, which costs are increasing ever more. © The Author(s) 2014.

Preliminary study on enhancing waste management best practice model in Malaysia construction industry

Science.gov (United States)

Jamaludin, Amril Hadri; Karim, Nurulzatushima Abdul; Noor, Raja Nor Husna Raja Mohd; Othman, Nurulhidayah; Malik, Sulaiman Abdul

2017-08-01

Construction waste management (CWM) is the practice of minimizing and diverting construction waste, demolition debris, and land-clearing debris from disposal and redirecting recyclable resources back into the construction process. Best practice model means best choice from the collection of other practices that was built for purpose of construction waste management. The practice model can help the contractors in minimizing waste before the construction activities will be started. The importance of minimizing wastage will have direct impact on time, cost and quality of a construction project. This paper is focusing on the preliminary study to determine the factors of waste generation in the construction sites and identify the effectiveness of existing construction waste management practice conducted in Malaysia. The paper will also include the preliminary works of planned research location, data collection method, and analysis to be done by using the Analytical Hierarchy Process (AHP) to help in developing suitable waste management best practice model that can be used in the country.

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

National inventory of radioactive wastes and recoverable materials 2006. Descriptive catalogue of radioactive waste families; Inventaire national des dechets radioactifs et des matieres valorisables 2006. Catalogue descriptif des familles de dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

Real comprehensive overview of radioactive wastes, the national inventory of radioactive wastes and recoverable materials describes the situation in France of the wastes that can be conditioned (in their definitive form) or not. It presents also the waste production quantities foreseen for 2010, 2020 and beyond. This document is a complement to the synthesis report and to the geographic inventory of radioactive wastes in France and details the classification of wastes by families (wastes with similar characteristics). For each family of wastes, the description comprises a general presentation and some photos. It comprises also some data such as the position of the family in the French classification, the industrial activity at the origin of the waste, the production situation of the waste in concern (finished, in progress, not started). Some information about the raw waste are given and the conditioning process used is described. Some figures complete the description, like: the past and future production quantities, the evaluation of the radioactivity of the waste family in 2004 and 2020, and the evaluation of the thermal power when available. Finally, some information are given about the presence of compounds with a specific risk of toxicity. (J.S.)

Present state of the design and realization of regional radioactive waste depositories and waste acceptance criteria for disposal

International Nuclear Information System (INIS)

Kortus, J.

1988-01-01

Surface type regional depositories for radioactive wastes from nuclear power plants are described in detail. The depository of the Mochovce nuclear power plant is located near the plant, that of the Dukovany nuclear power plant is directly on the premises of the plant. Particular attention is paid to the design of the monolithic reinforced concrete pits, draining of rainwater from their surface, draining of seeping rainwater from the pit environment by means of a double drainage system, and insulation of the pits against water. The construction of the Mochovce depository started in 1987; some experience gained from this activity is presented. The radioactive waste acceptance criteria for depositories of this kind, based on safety analysis, are given. (author). 2 figs

Radioactive waste disposal programme 2008 of the waste-management-compelled bodies. Technical report 08-01

International Nuclear Information System (INIS)

2008-10-01

and managing available interim storage capacity. The Swiss waste management concept assumes two deep geological repositories, one for low- and intermediate-level waste (L/ILW repository) and one for spent fuel, vitrified high level waste from reprocessing and long-lived intermediate-level waste (HLW repository). These two repositories could be implemented at different sites or at the same site if the geological situation is suitable. The proposed design concepts are based on the requirement that long-term safety is to be assured by a system of multiple passive safety barriers. There must be sufficient flexibility to allow information and experience arising in the future to be taken into account. Planning must also account for waste arising as a result of future developments in the areas of nuclear energy and application of radioactive materials. An allocation of the waste taking into account specific waste properties was undertaken in the context of preparing proposals for geological siting regions in order to derive the requirements on the geology. The implementation time plan assumes that the general licences will be granted for both repositories in 2018, start of operation of the L/ILW repository in 2035 and the HLW repository in 2050. The time plan takes into account site-specific studies for the L/ILW and HLW repositories, as well as the more generic, non-site-specific work that forms part of the research and development programme. It is also possible to take into account the waste arising that will result from future developments in nuclear energy and in the use of radioactive materials. Handling future licensing steps appropriately will allow any required expansion of repository capacity to be taken into account and the stepwise refinement of the waste allocation will also be possible. Radioactive waste must be held in interim storage until it can be emplaced in geological repositories. For the existing power plants and waste from medicine, industry and

The low to intermediate activity and short living waste storage facility. For a controlled management of radioactive wastes; Le centre de stockage des dechets de faible et moyenne activite a vie courte. Pour une gestion controlee des dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

Sited at about 50 km of Troyes (France), the Aube facility started in 1992 and has taken over the Manche facility for the surface storage of low to intermediate and short living radioactive wastes. The Aube facility (named CSFMA) is the answer to the safe management of these wastes at the industrial scale and for 50 years onward. This brochure presents the facility specifications, the wastes stored at the center, the surface storage concept, the processing and conditioning of waste packages, and the environmental monitoring performed in the vicinity of the site. (J.S.)

Strategies for the municipal waste management system to take advantage of carbon trading under competing policies: The role of energy from waste in Sydney

International Nuclear Information System (INIS)

El Hanandeh, Ali; El-Zein, Abbas

2009-01-01

Climate change is a driving force behind some recent environmental legislation around the world. Greenhouse gas emission reduction targets have been set in many industrialised countries. A change in current practices of almost all greenhouse-emitting industrial sectors is unavoidable, if the set targets is to be achieved. Although, waste disposal contributes around 3% of the total greenhouse gas emissions in Australia (mainly due to fugitive methane emissions from landfills), the carbon credit and trading scheme set to start in 2010 presents significant challenges and opportunities to municipal solid waste practitioners. Technological advances in waste management, if adopted properly, allow the municipal solid waste sector to act as carbon sink, hence earning tradable carbon credits. However, due to the complexity of the system and its inherent uncertainties, optimizing it for carbon credits may worsen its performance under other criteria. We use an integrated, stochastic multi-criteria decision-making tool that we developed earlier to analyse the carbon credit potential of Sydney municipal solid waste under eleven possible future strategies. We find that the changing legislative environment is likely to make current practices highly non-optimal and increase pressures for a change of waste management strategy.

Low-level and mixed waste incinerator survey report

International Nuclear Information System (INIS)

Garcia, E.C.

1988-10-01

The Low-Level and Mixed Waste Survey Task was initiated to investigate and document current and planned incinerator facilities in the Department of Energy Defense Programs (DOE-DP) system. A survey was mailed to the DOE field offices requesting information regarding existing or planned incinerator facilities located under their jurisdiction. The information requested included type, capacities, uses, costs, and mechanical description of the incinerators. The results of this survey are documented in this report. Nine sites responded to the survey, with eight sites listing nine incineration units in several stages of operations. The Idaho National Engineering Laboratory listed two operational facilities. There are four incinerators that are planned for start-up in 1991. Of the existing incinerators, three are used mostly for low-level wastes, while the planned units will be used for low-level, mixed, and hazardous wastes. This report documents the current state of the incineration facilities in the DOE-DP system and provides a preliminary strategy for management of low-level wastes and a basis for implementing this strategy. 5 refs., 4 figs., 14 tabs

Waste incineration and immobilization for nuclear facilities. Status report, April-September 1978

International Nuclear Information System (INIS)

Johnson, A.J.; Williams, P.M.; Burkhardt, S.C.; Ledford, J.A.; Gallagher, K.Y.

1980-01-01

The fluidized bed incinerator and waste immobilization processes are being developed to process various liquid and solid wastes that are generated by a nuclear facility. The versatility of the incinerator liquid waste handling system has been enhanced by recent changes made in the pumping and related piping system. Tributyl phosphate-solvent incineration has been evaluated thoroughly using the pilot plant fluidized bed incinerator. Vitrified glass pellets were made to determine operating parameters of a resistance-heated reactor and to produce samples for testing. Procedures were developed for testing the product pellets. A simplified start-up procedure was devised as development continued on a second type of reactor, the Joule-heated melter

New developments in low level radioactive waste management in Spain

International Nuclear Information System (INIS)

Zuloaga, P.

2006-01-01

El Cabril disposal facility was commissioned in 1992 and is a key element in LILW Management in Spain. It is a vault-type surface disposal facility with a total internal volume of 100,000 m 3 . The installation also has facilities for waste treatment and conditioning, verification and characterisation, interim storage and other ancillary equipment. This paper includes a brief description of the facility, the operational experience, the design improvements and new developments in waste acceptance procedures, safety assessment and the related research programme. The paper also refers to the new disposal facility intended for very low activity waste, under construction at the same site. This facility, a part of El Cabril nuclear installation, will have a maximum capacity for 130,000 m 3 of very low activity waste. Its construction started in February 2006, after the evaluation of the nuclear safety authority and the environmental impact statement procedure. (author)

STARTing Again: What Happens After START I Expires?

International Nuclear Information System (INIS)

Mladineo, Stephen V.; Durbin, Karyn R.; Eastman, Christina M.

2007-01-01

The Strategic Arms Reduction Treaty (START I), a seminal arms control agreement that substantially reduced the levels of deployed strategic nuclear arms in the United States and Russia, will expire in December 2009. At this time, it is unclear what - if anything - will replace it. While the treaty remains relevant, more than a simple extension is appropriate. Instead the authors advocate for a successor regime that builds on the START I legacy but does not rely on the traditional tools of arms control. This paper examines the strategic context in which a successor regime would be developed and proposes several recommendations for future action

Radioactive waste management status and trends. An overview of international status and trends in radioactive waste management. No. 1

International Nuclear Information System (INIS)

2001-09-01

The IAEA attaches a high importance to the dissemination of information that can assist Member States with the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support the nuclear fuel cycle and nuclear applications. This status and trends report has been issued in support of the Agency's strategy. It also represents the start of a process to improve the reporting of status and trends in radioactive waste management. The objectives of the report were: to identify subject areas deemed to be of interest to Member States and the Agency; to report the status of and trends in radioactive waste management according to these subject areas; and to base this reporting, to the greatest extent practicable, on quantitative data. This issue of the status and trends report is intended for persons directly involved in radioactive waste management and regulation as well as members of the general public who are relatively familiar with the nuclear industry

Influence of feedstock on the copper removal capacity of waste-derived biochars.

Science.gov (United States)

Arán, Diego; Antelo, Juan; Fiol, Sarah; Macías, Felipe

2016-07-01

Biochar samples were generated by low temperature pyrolysis of different types of waste. The physicochemical characteristics of the different types of biochar affected the copper retention capacity, by determining the main mechanism involved. The capacity of the biochar to retain copper present in solution depended on the size of the inorganic fraction and varied in the following order: rice biochar>chicken manure biochar>olive mill waste biochar>acacia biochar>eucalyptus biochar>corn cob biochar. The distribution of copper between the forms bound to solid biochar, dissolved organic matter and free organic matter in solution also depended on the starting material. However, the effect of pH on the adsorption capacity was independent of the nature of the starting material, and the copper retention of all types of biochar increased with pH. Copyright © 2016 Elsevier Ltd. All rights reserved.

Lifelong doubling of mortality in men entering adult life as obese

DEFF Research Database (Denmark)

Zimmermann, E; Holst, C; Sørensen, T I A

2011-01-01

The association between obesity in adults and excess morbidity and mortality is well established, but the impact of being obese in early adulthood on health throughout adult life needs elucidation. We investigated the all-cause mortality until 80 years of age in men starting adult life as obese....

National facilities for the management of institutional radioactive waste in Romania: 25 years of operation for radioactive waste treatment plant, Bucharest-Magurele, 15 years of operation for national radioactive repository, Baita-Bihor

International Nuclear Information System (INIS)

Rotarescu, Gh.; Turcanu, C.; Dragolici, F.; Lungu, L.; Nicu, M.; Cazan, L.; Matei, G.; Guran, V.

1999-01-01

The management of the non-fuel cycle radioactive wastes in Romania is centralized at IFIN-HH in the Radioactive Waste Treatment Plant (STDR) Bucharest-Magurele and the National Repository of Radioactive Waste (DNDR) Baita-Bihor. From November 1974 to November 1999 there were treated at STDR nearly 26,000 m 3 LLAW, 2,100 m 3 LLSW and 4,000 spent sources resulting over 5,500 conditioned packages disposed at DNDR. After 25 years of operation for STDR and 15 years of operation for DNDR an updating programme started in 1991. The R and D programme will improve the basic knowledge and waste management practices for the increasing of nuclear safety in the field. (authors)

Exploring the awareness level of biomedical waste management: Case of Indian healthcare

Directory of Open Access Journals (Sweden)

Rahul S. Mor

2017-10-01

Full Text Available This study aims to investigate the awareness level of Biomedical waste managements in healthcare facilities, and their perception among hospital waste management team, doctors, nurses, lab techni-cians and waste handlers in Northwest Delhi region in India. The study has been conducted through a questionnaire survey followed by the descriptive statistical analysis method. Question-naire contains of 38 questions, where the first section deals with the hospital waste management team, the second section is for doctors, nurses and lab technicians, and the third section is for the waste handlers. Out of 311 respondents, there were 16 hospital waste management teams, 81 doc-tors, 92 nurses, 49 lab technicians and 73 waste handlers. It was surprising that only 40% (n=10 hospitals had any kind of waste treatment & disposal facility onsite, only 10% hospitals were using the latest technology and 60% hospitals shred the Biomedical waste before disposal. It was good to see that none of the hospital waste managements disposed the waste with general waste, and 40% of them were exhausting through government agencies and the remaining 60% were using private agencies to dispose the waste. Finally, all the hospitals maintained the record of waste generated. It is concluded that there was a lack of awareness about the biomedical waste generation, legislation and management among healthcare personnel, and they all needed regular audits and training pro-grams at all levels, and a proper management starting from waste generation to its disposal at sites.

Process and technological aspects of municipal solid waste gasification. A review

International Nuclear Information System (INIS)

Arena, Umberto

2012-01-01

Highlights: ► Critical assessment of the main commercially available MSW gasifiers. ► Detailed discussion of the basic features of gasification process. ► Description of configurations of gasification-based waste-to-energy units. ► Environmental performance analysis, on the basis of independent sources data. - Abstract: The paper proposes a critical assessment of municipal solid waste gasification today, starting from basic aspects of the process (process types and steps, operating and performance parameters) and arriving to a comparative analysis of the reactors (fixed bed, fluidized bed, entrained bed, vertical shaft, moving grate furnace, rotary kiln, plasma reactor) as well as of the possible plant configurations (heat gasifier and power gasifier) and the environmental performances of the main commercially available gasifiers for municipal solid wastes. The analysis indicates that gasification is a technically viable option for the solid waste conversion, including residual waste from separate collection of municipal solid waste. It is able to meet existing emission limits and can have a remarkable effect on reduction of landfill disposal option.

Office of Waste Isolation. Progress report, November 1977. [National waste terminal storage

Energy Technology Data Exchange (ETDEWEB)

Rhines, R.C.; Asher, J.M. (eds.)

1977-12-28

This program is part of the National Waste Terminal Storage program. The Geologic Review Group meeting was held in New Orleans, November 16-17. Start-up of the near-surface heater experiment in the Conasauga Shale formation is under way at Oak Ridge. The first shipment of experimental equipment from Oak Ridge to Avery Island, Louisiana, for the dome salt in-situ test was successfully completed. On November 9-10, a design status review on the spent fuel repository conceptual design was held with Kaiser Engineers, Inc. On November 2, OWI personnel reviewed the progress on the Economic Studies with TRW representatives.

WasteChem Corporation's Volume Reduction and Solidification (VRS) system for low-level radwaste treatment: Final report

International Nuclear Information System (INIS)

1988-01-01

Since 1965, low and medium level radwastes from nuclear power stations, reprocessing plants and nuclear research centers have been stabilized using the Volume Reduction and Solidification (VRS) system. The VRS system uses an extruder/evaporator to evaporate the liquids from waste influents, while simultaneously incorporating the remaining radioactive solids in an asphalt binder. In the period 1965 to 1986 a minimum of 700,000 cubic feet of wastes have been processed with the VRS system. This report provides current operating data from various systems including the volume reduction factors achieved, and the progress of start-ups in the US. The report also provides previously unpublished experience with mixed wastes including uranium raffinate and nitrate-bearing sludges from surface impoundments. VRS systems in the US are currently operating at the Palisades and Hope Creek nuclear stations. These systems produce a variety of waste types including boric acid, bead resin, sodium sulfate and powdered resins. There are three start-ups of VRS systems scheduled in the US in 1987. These systems are at Fermi 2, Seabrook, and Nine Mile Point 2. Overseas, the startup of new systems continues with three VRS process lines coming on-line at the LaHague Reprocessing Center in France in 1986 and a start-up scheduled for 1987 at the Laguna Verde plant in Mexico. The US systems are operating continuously and with little required maintenance. Data on maintenance and the operator exposure are provided in this report. 6 refs., 11 figs., 13 tabs

Lipases Immobilization for Effective Synthesis of Biodiesel Starting from Coffee Waste Oils

Directory of Open Access Journals (Sweden)

Lucia Gardossi

2013-08-01

Full Text Available Immobilized lipases were applied to the enzymatic conversion of oils from spent coffee ground into biodiesel. Two lipases were selected for the study because of their conformational behavior analysed by Molecular Dynamics (MD simulations taking into account that immobilization conditions affect conformational behavior of the lipases and ultimately, their efficiency upon immobilization. The enzymatic synthesis of biodiesel was initially carried out on a model substrate (triolein in order to select the most promising immobilized biocatalysts. The results indicate that oils can be converted quantitatively within hours. The role of the nature of the immobilization support emerged as a key factor affecting reaction rate, most probably because of partition and mass transfer barriers occurring with hydrophilic solid supports. Finally, oil from spent coffee ground was transformed into biodiesel with yields ranging from 55% to 72%. The synthesis is of particular interest in the perspective of developing sustainable processes for the production of bio-fuels from food wastes and renewable materials. The enzymatic synthesis of biodiesel is carried out under mild conditions, with stoichiometric amounts of substrates (oil and methanol and the removal of free fatty acids is not required.

DOE systems approach to a low-level waste management information system: summary paper

International Nuclear Information System (INIS)

Esparza, V.

1987-01-01

The LLWMP is performing an assessment of waste information systems currently in use at each DOE site for recording LLW data. The assessment is being conducted to determine what changes to the waste information systems, if any, are desirable to support implementation of this systems approach to LLW management. Recommendations will be made to DOE from this assessment and what would be involved to modify current DOE waste generator information practices to support an appropriately structured overall DOE LLW data systems. In support of reducing the uncertainty of decision-making, DOE has selected a systems approach to keep pace with an evolving regulatory climate to low-level waste. This approach considers the effects of each stage of the entire low-level waste management process. The proposed systems approach starts with the disposal side of the waste management system and progresses towards the waste generation side of the waste management system. Using this approach provides quantitative performance to be achieved. In addition, a systems approach also provides a method for selecting appropriate technology based on engineering models

Validation of new ceramic materials from tungsten mining wastes. Mechanical properties

International Nuclear Information System (INIS)

Duran Suarez, J. A.; Montoya Herrera, J.; Silva, A. P.; Peralbo Cano, R.; Castro-Gomes, J. P.

2014-01-01

New ceramic materials obtained from tungsten mining wastes, from region of Beira Interior in Portugal, with no commercial use, responsible for landscape and environmental problems are presented. These preshaped new ceramic products, prepared in a wide thermal range (800 degree centigrade to 1300 degree centigrade) was evaluated by mechanical test, but also was characterized the starting raw materials: tungsten wastes mining and industrial kaolin. Results, which also include a mineralogical characterization of ceramic products and morphologic evaluation of neoformed by scanning electron microscopy, show firstly, the feasibility of converting a large number of these wastes in marketable ceramics. Thanks to the experimentation carried out, the ability to generate ceramic materials is emphasized, without the presence of mineral clay, due to the particular composition of these waste of mining with content of acid, neutral and basic oxides. (Author)

Containers for packaging of solid and intermediate level radioactive wastes

International Nuclear Information System (INIS)

1993-01-01

Low and intermediate level radioactive wastes are generated at all stages in the nuclear fuel cycle and also from the medical, industrial and research applications of radiation. These wastes can potentially present risks to health and the environment if they are not managed adequately. Their effective management will require the wastes to be safely stored, transported and ultimately disposed of. The waste container, which may be defined as any vessel, drum or box, made from metals, concrete, polymers or composite materials, in which the waste form is placed for interim storage, for transport and/or for final disposal, is an integral part of the whole package for the management of low and intermediate level wastes. It has key roles to play in several stages of the waste management process, starting from the storage of raw wastes and ending with the disposal of conditioned wastes. This report provides an overview of the various roles that a container may play and the factors that are important in each of these roles. This report has two main objectives. The first is to review the main requirements for the design of waste containers. The second is to provide advice on the design, fabrication and handling of different types of containers used in the management of low and intermediate level radioactive solid wastes. Recommendations for design and testing are given, based on the extensive experience available worldwide in waste management. This report is not intended to have any regulatory status or objectives. 56 refs, 16 figs, 10 tabs

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

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

DASAO: software tool for the management of safeguards, waste and decommissioning

International Nuclear Information System (INIS)

Noynaert, Luc; Verwaest, Isi; Libon, Henri; Cuchet, Jean-Marie

2013-01-01

Decommissioning of nuclear facilities is a complex process involving operations such as detailed surveys, decontamination and dismantling of equipment's, demolition of buildings and management of resulting waste and nuclear materials if any. This process takes place in a well-developed legal framework and is controlled and followed-up by stakeholders like the Safety Authority, the Radwaste management Agency and the Safeguards Organism. In the framework of its nuclear waste and decommissioning program and more specifically the decommissioning of the BR3 reactor, SCK-CEN has developed different software tools to secure the waste and material traceability, to support the sound management of the decommissioning project and to facilitate the control and the follow-up by the stakeholders. In the case of Belgium, it concerns the Federal Agency for Nuclear Control, the National Agency for radioactive waste management and fissile material and EURATOM and IAEA. In 2005, Belgonucleaire decided to shutdown her Dessel MOX fuel fabrication plant and the production stopped in 2006. According to the final decommissioning plan ('PDF') approved by NIRAS, the decommissioning works should start in 2008 at the earliest. In 2006, the management of Belgonucleaire identified the need for an integrated database and decided to entrust SCK-CEN with its development, because SCK-CEN relies on previous experience in comparable applications namely already approved by authorities such as NIRAS, FANC and EURATOM. The main objectives of this integrated software tool are: - simplified and updated safeguards; - waste and material traceability; - computerized documentation; - support to project management; - periodic and final reporting to waste and safety authorities. The software called DASAO (Database for Safeguards, Waste and Decommissioning) was successfully commissioned in 2008 and extensively used from 2009 to the satisfaction of Belgonucleaire and the stakeholders. SCK-CEN is

Bioethanol production from renewable sources as alternative valorization of waste of starting dates in south Algeria

Science.gov (United States)

Mehani, Insaf; Bouchekima, Bachir

2018-05-01

The necessary reduction and progressive consumption of fossil fuels, whose scarcity is inevitable, involves mobilizing a set of alternatives. Renewable energy, including bio energy is an alternative to the depletion of fossil fuels and a way to fight against the harmful effects of pollution that undergoes the environment. In Algeria, the conditioning units of dates generate significant quantities of waste arising from sorting deviations. This biomass, until then considered as a waste with high impact on the environment can be transformed into high value added product. It is possible to develop common dates of low commercial value, and put on the local and international market a new generation of products with high added values such as bio ethanol. Besides its use in chemical synthesis, bio ethanol can be blended with gasoline to produce a clean fuel while improving the octane. The objective of the present work is to study the feasibility and productivity of generating bio ethanol in laboratory from the transformation of common date using anaerobic fermentation and distillation processes. After an alcoholic fermentation of the substrate of the date using bakery yeast at 30°C for 72 h, the distilled and rectified date juice generated the highest ethanol 88° with acceptable productions.

Waste management of shrimp farms as starting point to develop integrated farming systems (case study: Kuwaru Coast, Bantul, Yogyakarta, Indonesia

Directory of Open Access Journals (Sweden)

H.G. Saiya

2015-10-01

Full Text Available Intensive waste management is a solution to maintain an area of ecological harmony but still can produce economic benefits that are beneficial to social welfare. So in this research, waste of shrimp farms which was just processed by using zeolite, was treated again with a few treatments, i.e. simple filters, constructed wetlands, shell, fish and composting. Simple filters were composed of stone, gravel, coral, charcoal, sand and coconut fibers. Constructed wetland system used was hybrid type which combines type of horizontal flow and type of vertical flow. The shell used was Polymesoda erosa. The fish used was Tilapia. In the composting sediment activator, biang kompos was used with the composting time of one month. The results indicated that the system of simple filters, constructed wetlands, shells and fish proved to be quite effective to reduce levels of pollutants in wastewater and will be more effective if treatment was accompanied with a proper aeration. While, the sediment composted into fertilizer needed to be composted with a longer time than normal composting time. This was because the composted materials were derived from waste having a very low nutrient, so it took longer to restore nutrients. The results also indicated the potential of shrimp farm waste of PT. IBD to be processed into clean water and fertilizer. With the appropriate policies and strategies, this can lead to the development of an integrated farming system to support sustainable coastal ecologically, economically and socially.

Association between Duration of Predialysis Care and Mortality after Dialysis Start.

Science.gov (United States)

Liu, Ping; Quinn, Robert R; Oliver, Matthew J; Ronksley, Paul E; Hemmelgarn, Brenda R; Quan, Hude; Hiremath, Swapnil; Bello, Aminu K; Blake, Peter G; Garg, Amit X; Johnson, John; Verrelli, Mauro; Zacharias, James M; Abd ElHafeez, Samar; Tonelli, Marcello; Ravani, Pietro

2018-03-05

Early nephrology referral is recommended for people with CKD on the basis of observational studies showing that longer nephrology care before dialysis start (predialysis care) is associated with lower mortality after dialysis start. This association may be observed because predialysis care truly reduces mortality or because healthier people with an uncomplicated course of disease will have both longer predialysis care and lower risk for death. We examined whether the survival benefit of longer predialysis care exists after accounting for the potential confounding effect of disease course that may also be affected by predialysis care. We performed a retrospective cohort study and used data from 3152 adults with end stage kidney failure starting dialysis between 2004 and 2014 in five Canadian dialysis programs. We obtained duration of predialysis care from the earliest nephrology outpatient visit to dialysis start; markers of disease course, including inpatient or outpatient dialysis start and residual kidney function around dialysis start; and all-cause mortality after dialysis start. The percentages of participants with 0, 1-119, 120-364, and ≥365 days of predialysis care were 23%, 8%, 10%, and 59%, respectively. When we ignored markers of disease course as in previous studies, longer predialysis care was associated with lower mortality (hazard ratio 120-364 versus 0-119 days , 0.60; 95% confidence interval, 0.46 to 0.78]; hazard ratio ≥365 versus 0-119 days , 0.60; 95% confidence interval, 0.51 to 0.71; standard Cox model adjusted for demographics and laboratory and clinical characteristics). When we additionally accounted for markers of disease course using the inverse probability of treatment weighted Cox model, this association was weaker and no longer significant (hazard ratio 120-364 versus 0-119 days , 0.84; 95% confidence interval, 0.60 to 1.18; hazard ratio ≥365 versus 0-119 days , 0.88; 95% confidence interval, 0.69 to 1.13). The association between

From START to NEW START. The dilemma and future of nuclear disarmament

International Nuclear Information System (INIS)

Plettenberg, Lars

2012-01-01

The report describes the existing four agreements on nuclear disarmament: START I (1991). START II (1993), SORT (2002) and NEW START (2010). The chapter on the dependence between nuclear disarmament and strategic stability covers the issues mutual assured destruction (MAD), credibility, overkill capacity; the role of nuclear weapons in the national strategies of the USA and NATO, Russia, Great Britain, France, China and the other nuclear states. Ways out of MAD include disarmament, de-alerting and mutual assured protection (MAP).

Comparing Non-Steady State Emissions under Start-Up and Shut-Down Operating Conditions with Steady State Emissions for Several Industrial Sectors: A Literature Review

Directory of Open Access Journals (Sweden)

Juwairia Obaid

2017-02-01

Full Text Available This study investigates the emissions of various industrial facilities under start-up, shut-down, and normal operations. The industries that have been investigated include power and/or heat generation, energy-from-waste generation, nuclear power generation, sulphuric acid production, ethylene production, petrochemical production, and waste incineration. The study investigated multiple facilities worldwide for each of these industrial categories. The different potential contaminants characteristic of each industry type have been investigated and the emissions of these contaminants under non-steady state have been compared to the steady state emissions. Where available, trends have been developed to identify the circumstances, i.e., the industrial sector and contaminant, under which the assessment and consideration of emissions from start-up and shut-down events is necessary for each industry. These trends differ by industrial sector and contaminant. For example, the study shows that sulphur dioxide (SO2 emissions should be assessed for the start-up operations of sulphuric acid production plants, but may not need to be assessed for the start-up operations of a conventional power generation facility. The trends developed as part of this research paper will help air permit applicants to effectively allocate their resources when assessing emissions related to non-steady state operations. Additionally, it will ensure that emissions are assessed for the worst-case scenario. This is especially important when emissions under start-up and shut-down operations have the potential to exceed enforceable emission limits. Thus, assessing emissions for the worst-case scenario can help in preventing the emissions from adversely impacting public health and the environment.

Bench-scale arc melter for R&D in thermal treatment of mixed wastes

Energy Technology Data Exchange (ETDEWEB)

Kong, P.C.; Grandy, J.D.; Watkins, A.D.; Eddy, T.L.; Anderson, G.L.

1993-05-01

A small dc arc melter was designed and constructed to run bench-scale investigations on various aspects of development for high-temperature (1,500-1,800{degrees}C) processing of simulated transuranic-contaminated waste and soil located at the Radioactive Waste Management Complex (RWMC). Several recent system design and treatment studies have shown that high-temperature melting is the preferred treatment. The small arc melter is needed to establish techniques and procedures (with surrogates) prior to using a similar melter with the transuranic-contaminated wastes in appropriate facilities at the site. This report documents the design and construction, starting and heating procedures, and tests evaluating the melter`s ability to process several waste types stored at the RWMC. It is found that a thin graphite strip provides reliable starting with initial high current capability for partially melting the soil/waste mixture. The heating procedure includes (1) the initial high current-low voltage mode, (2) a low current-high voltage mode that commences after some slag has formed and arcing dominates over the receding graphite conduction path, and (3) a predominantly Joule heating mode during which the current can be increased within the limits to maintain relatively quiescent operation. Several experiments involving the melting of simulated wastes are discussed. Energy balance, slag temperature, and electrode wear measurements are presented. Recommendations for further refinements to enhance its processing capabilities are identified. Future studies anticipated with the arc melter include waste form processing development; dissolution, retention, volatilization, and collection for transuranic and low-level radionuclides, as well as high vapor pressure metals; electrode material development to minimize corrosion and erosion; refractory corrosion and/or skull formation effects; crucible or melter geometry; metal oxidation; and melt reduction/oxidation (redox) conditions.

MIIT: International in-situ testing of nuclear waste glasses-performance of SRS simulated waste glass after 5 years of burial at the waste isolation pilot plant (WIPP)

International Nuclear Information System (INIS)

Wicks, G.G.; Lodding, A.R.; Macedo, P.B.; Clark, D.E.

1993-01-01

In July of 1986, the first in-situ test involving burial of simulated high-level waste [HLW] forms conducted in the United States was started. This program, called the Materials Interface Interactions Test or MIIT, comprises the largest, most cooperative field-testing venture in the international waste management community. Included in the study are over 900 waste form samples comprising 15 different systems supplied by seven nations. Also included are about 300 potential canister or overpack metal samples along with more than 500 geologic and backfill specimens. There are almost 2000 relevant interactions that characterize this effort which has been conducted in the bedded salt site at the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. The MIIT program represents a joint effort managed by the Savannah River Technology Center (SRTC) in Aiken, S.C., and Sandia National Laboratories (SNL) in Albuquerque, N.M.. and sponsored by the US Department of Energy. Involved in MIIT are participants from national and federal laboratories, universities, and representatives from laboratories in France, Germany, Canada, Belgium, Japan, Sweden, the United Kingdom, and the United States. In July of 1991, the experimental portion of the 5-year MIIT study was completed on schedule. During this time interval, many in-situ measurements were performed, thousands of brine analyses conducted, and hundreds of waste glass and package components exhumed and evaluated after 6 mo., 1 yr., 2 yr. and 5 yr. burial periods. Although analyses are still in progress, the performance of SRS waste glass based on all data currently available has been seen to be excellent thus far. Initial analyses and assessment of Savannah River (SR) waste glass after burial in WIPP at 90 degrees C for 5 years is presented

Optimization of Waste and Materials Disposition in France - Policy, Strategies, and Techniques

International Nuclear Information System (INIS)

DUTZER, Michel; Rives, Jean Francois

2014-01-01

2007, the present version, the third one, is applicable for the period between 2013 and 2015. As an important input for the PNGMDR a National Inventory of Radioactive Material and Waste is updated every three years by Andra. Dedicated chapters of the PNGMDR focus on disposal in available repositories, on the incineration of waste, on the recycling of waste after melting. Centre de l'Aube disposal facility can accommodate for low and intermediate short lived waste. It started up in 1992. Its capacity is 1,000,000 m 3 . At the end of 2013 280,000 m 3 have been disposed of. According to the National Inventory it should be able to accommodate all waste for presently operated or decided nuclear facilities, including decommissioning waste. Centre de Morvilliers disposal facility started up in 2003 and is dedicated for very low level waste. It has a capacity of 650,000 m 3 and was designed for 30 years of operation. At the end of 2013 252,000 m 3 have been disposed of. Waste production identified in the National inventory doubled since the start up and suggest an anticipated saturation of this facility. Therefore the PNGMDR recommends efforts on several fronts: densification of waste, increase of disposal capacities and recycling of metals. The enforcement of the French regulation leads to recycle very low level metals, even after decontamination, within the nuclear industry. Furthermore secondary waste should also be considered as secondary waste. Reinforced traceability has to be kept through all sequences of recycling: waste melting, production of new metallic parts and their incorporation in a nuclear facility. Furthermore the amount of metallic waste is low (in the range of 10,000 tons per year for steel, which is one thousandth of steel that is yearly recycled in France) is a handicap for the development of a relevant industrial route. However France experienced successfully the recycling of steel in Centraco/Socodei facility where 21,700 tons of metals have been

Industrial Program of Waste Management - Cigeo Project - 13033

Energy Technology Data Exchange (ETDEWEB)

Butez, Marc [Agence nationale pour la gestion des dechets radioactifs - Andra, 1-7, rue Jean Monnet 92298 Chatenay-Malabry (France); Bartagnon, Olivier; Gagner, Laurent [AREVA NC Tour AREVA 1 place de la Coupole 92084 Paris La Defense (France); Advocat, Thierry; Sacristan, Pablo [Commissariat a l' energie atomique et aux energies alternatives - CEA, CEA-SACLAY 91191 Gif sur Yvette Cedex (France); Beguin, Stephane [Electricite de France - EDF, Division Combustible Nucleaire, 1, Place Pleyel Site Cap Ampere93282 Saint Denis (France)

2013-07-01

The French Planning Act of 28 June 2006 prescribed that a reversible repository in a deep geological formation be chosen as the reference solution for the long-term management of high-level and intermediate-level long-lived radioactive waste. It also entrusted the responsibility of further studies and design of the repository (named Cigeo) upon the French Radioactive Waste Management Agency (Andra), in order for the review of the creation-license application to start in 2015 and, subject to its approval, the commissioning of the repository to take place in 2025. Andra is responsible for siting, designing, implementing, operating the future geological repository, including operational and long term safety and waste acceptance. Nuclear operators (Electricite de France (EDF), AREVA NC, and the French Commission in charge of Atomic Energy and Alternative Energies (CEA) are technically and financially responsible for the waste they generate, with no limit in time. They provide Andra, on one hand, with waste packages related input data, and on the other hand with their long term industrial experiences of high and intermediate-level long-lived radwaste management and nuclear operation. Andra, EDF, AREVA and CEA established a cooperation agreement for strengthening their collaborations in these fields. Within this agreement Andra and the nuclear operators have defined an industrial program for waste management. This program includes the waste inventory to be taken into account for the design of the Cigeo project and the structural hypothesis underlying its phased development. It schedules the delivery of the different categories of waste and defines associated flows. (authors)

Industrial Program of Waste Management - Cigeo Project - 13033

International Nuclear Information System (INIS)

Butez, Marc; Bartagnon, Olivier; Gagner, Laurent; Advocat, Thierry; Sacristan, Pablo; Beguin, Stephane

2013-01-01

The French Planning Act of 28 June 2006 prescribed that a reversible repository in a deep geological formation be chosen as the reference solution for the long-term management of high-level and intermediate-level long-lived radioactive waste. It also entrusted the responsibility of further studies and design of the repository (named Cigeo) upon the French Radioactive Waste Management Agency (Andra), in order for the review of the creation-license application to start in 2015 and, subject to its approval, the commissioning of the repository to take place in 2025. Andra is responsible for siting, designing, implementing, operating the future geological repository, including operational and long term safety and waste acceptance. Nuclear operators (Electricite de France (EDF), AREVA NC, and the French Commission in charge of Atomic Energy and Alternative Energies (CEA) are technically and financially responsible for the waste they generate, with no limit in time. They provide Andra, on one hand, with waste packages related input data, and on the other hand with their long term industrial experiences of high and intermediate-level long-lived radwaste management and nuclear operation. Andra, EDF, AREVA and CEA established a cooperation agreement for strengthening their collaborations in these fields. Within this agreement Andra and the nuclear operators have defined an industrial program for waste management. This program includes the waste inventory to be taken into account for the design of the Cigeo project and the structural hypothesis underlying its phased development. It schedules the delivery of the different categories of waste and defines associated flows. (authors)

Rokkasho low-level radioactive waste disposal in Japan

International Nuclear Information System (INIS)

Takahashi, Y.

1994-01-01

Japan Nuclear Fuel Limited commenced the operation of the shallow land disposal of low-level radioactive waste from reactor operation, in 1992 at Rokkasho site in Aomori Prefecture. JNFL is private company whose main activities within the responsibility of JNFL are: 1) Disposal of low-level radioactive waste, 2) Uranium enrichment, 3) Reprocessing of spent nuclear fuels, 4) Temporary storage of returned wastes from COGEMA and BNFL by reprocessing contracts, prior to disposal. JNFL selected the site for the disposal of LLW at Rokkasho in Aomori Prefecture, then bought land of 3.4 million m 2 . Among waste spectrum, LLWs from nuclear power plants, from uranium enrichment and from reprocessing are to be managed by JNFL, including dismantling of these facilities, and JNFL has plan to dispose about 600 thousand m 3 of wastes ultimately. On the middle of November 1990 JNFL got the permission of the application for 40 thousand m 3 (equivalent to 200,000 drums each with a 200-liter capacity) of reactor operating wastes which is solidified with cement, bitumen or plastics as a first stage. And after the construction work for about 2 years, the operations started at Dec. 8th, 1992. The Disposal center has already accepted about 24,000 LLW drums as of the end of February, 1994. (author)

Microbial biotechnology addressing the plastic waste disaster

OpenAIRE

Narancic, Tanja; O'Connor, Kevin E.

2017-01-01

Oceans are a major source of biodiversity, they provide livelihood, and regulate the global ecosystem by absorbing heat and CO 2. However, they are highly polluted with plastic waste. We are discussing here microbial biotechnology advances with the view to improve the start and the end of life of biodegradable polymers, which could contribute to the sustainable use of marine and coastal ecosystems (UN Sustainability development goal 14).

Investigations of potential below regulatory concern (de minimus) wastes

International Nuclear Information System (INIS)

Gruhlke, J.M.; Galpin, F.L.

1983-01-01

Low-level radioactive waste (LLW) includes a wide variety of waste types. Many organizations are contemplating the merits of declaring certain LLW as de minimus. The concept of de minimus has considerable support, as evidenced by the comments on NRC's rulemaking for 10 CFR Part 61, Licensing Requirements for Land Disposal of Radioactive Waste. Practical and philosophical considerations lend weight to the further investigation of the de minimus concept for LLW. The Environmental Protection Agency (EPA) recognizes the interest and efforts in the concept of de minimus. Because the term de minimus may imply a lack of concern for the risks of disposal, we use the term Below Regulatory Concern (BRC). EPA has developed technical information, cost data, and a methodology for selecting promising candidate waste streams. The NRC's breakdown of LLW, as provided in the supporting documentation for 10 CFR Part 51, serves as a starting point for evaluating individual waste streams. Waste streams may then be ranked on the basis of individual dose, population health impact, and cost/benefit. A set of waste streams consistently ranks near the top in all categories and deserves further analysis. This screening is the initial step in an overall effort to develop a basis for determining the appropriateness and form of generic BRC criteria. 14 references, 8 tables

Long-time leaching on full size radioactive waste blocks

International Nuclear Information System (INIS)

Bernard, Andre; Nomine, J.-C.; Cornec, Georges; Bonnet, Andre; Farges, Louis.

1980-12-01

Leaching is generally accepted as the fundamental characteristic when judging the quality of radioactive waste packaging. Long duration leaching tests have been carried out on full size waste blocks at the Commissariat a l'Energie Atomique. The monoliths studied are 200 litre cylinders made up of α, β and γ emitting liquid or solid waste embedded in cement or bitumen. Leaching takes place in accordance with rules based on I.A.E.A. recommendations embodying the specific concerns of safety and radiological capacity of storage sites. The tests are carried out at a Testing Station purpose built at Saclay. It includes several loops with instrumentation (volume: 3000 litres). The counting and analyses of the leached products have enabled the aggregated released fractions of the radionuclides and the structural and chemical modifications of the matrices to be assessed. The fractions of 137 Cs and 239 Pu released at 18 months are 10 -2 and 5x10 -6 for the cement coated wastes, and 10 -4 and 10 -5 for the bitumen coated wastes. The evaluation of the changes in the matrices made it possible, in particular, to observe the start of carbonation in the cement coated wastes. These trials are to be pursued for several years so as to obtain a better understanding of the exchange mechanics between the packaged wastes and the environment [fr

Tank Waste Remediation System retrieval and disposal mission technical baseline summary description

International Nuclear Information System (INIS)

McLaughlin, T.J.

1998-01-01

This document is prepared in order to support the US Department of Energy's evaluation of readiness-to-proceed for the Waste Retrieval and Disposal Mission at the Hanford Site. The Waste Retrieval and Disposal Mission is one of three primary missions under the Tank Waste Remediation System (TWRS) Project. The other two include programs to characterize tank waste and to provide for safe storage of the waste while it awaits treatment and disposal. The Waste Retrieval and Disposal Mission includes the programs necessary to support tank waste retrieval, wastefeed, delivery, storage and disposal of immobilized waste, and closure of tank farms. This mission will enable the tank farms to be closed and turned over for final remediation. The Technical Baseline is defined as the set of science and engineering, equipment, facilities, materials, qualified staff, and enabling documentation needed to start up and complete the mission objectives. The primary purposes of this document are (1) to identify the important technical information and factors that should be used by contributors to the mission and (2) to serve as a basis for configuration management of the technical information and factors

The impact of dry-land sprint start training on the short track speed skating start.

Science.gov (United States)

Haug, William B; Drinkwater, Eric J; Cicero, Nicholas J; Barthell, J Anthony; Chapman, Dale W

2017-05-05

This investigation sought to determine the effects of dry-land sprint start training on short track speed skating (STSS) start performance. Nine highly trained short track athletes completed a control period of normal STSS training followed by a four-week training intervention. Before and after the control and intervention periods, athletes performed three electronically timed dry-land and on-ice 14.43 m maximal sprint start efforts. The intervention consisted of two sprint sessions per week consisting of nine electronically timed 14.43 m dry-land sprint starts in addition to normal STSS training. The control period resulted in no substantial change in on-ice start performance (Mean Δ: -0.01 s, 95% Confidence Limits (CL): -0.08 to 0.05 s; Effect Size (ES): -0.05; Trivial) however, a small change was observed in dry-land start performance (Mean Δ: -0.07 s, 95% CL: -0.13 to -0.02 s; ES: -0.49). Following brief specific dry-land sprint start training a small improvement was observed in both on-ice (Mean Δ: -0.07 s, 95% CL: -0.13 to -0.01 s; ES: -0.33) and dry-land (Mean Δ: -0.04 s, 95% CL: -0.09 to 0.00 s; ES: -0.29) start performance. This investigation suggests STSS start performance can be improved through a brief dry-land sprint start training program.

Nuclear waste disposal technology for Pacific Basin countries

International Nuclear Information System (INIS)

Langley, R.A. Jr.; Brothers, G.W.

1981-01-01

Safe long-term disposal of nuclear wastes is technically feasible. Further technological development offers the promise of reduced costs through elimination of unnecessary conservatism and redundance in waste disposal systems. The principal deterrents to waste disposal are social and political. The issues of nuclear waste storage and disposal are being confronted by many nuclear power countries including some of the Pacific Basin nuclear countries. Both mined geologic and subseabed disposal schemes are being developed actively. The countries of the Pacific Basin, because of their geographic proximity, could benefit by jointly planning their waste disposal activities. A single repository, of a design currently being considered, could hold all the estimated reprocessing waste from all the Pacific Basin countries past the year 2010. As a start, multinational review of alterntive disposal schemes would be beneficial. This review should include the subseabed disposal of radwastes. A multinational review of radwaste packaging is also suggested. Packages destined for a common repository, even though they may come from several countries, should be standardized to maximize repository efficiency and minimize operator exposure. Since package designs may be developed before finalization of a repository scheme and design, the packages should not have characteristics that would preclude or adversely affect operation of desirable repository options. The sociopolitical problems of waste disposal are a major deterrent to a multinational approach to waste disposal. The elected representatives of a given political entity have generally been reluctant to accept the waste from another political entity. Initial studies would, nevertheless, be beneficial either to a common solution to the problem, or to aid in separate solutions

Commercial Spent Nuclear Fuel Waste Package Misload Analysis

International Nuclear Information System (INIS)

J.K. Knudson

2003-01-01

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M and O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis

Zeolite A synthesized from wastes of kaolin improvement process; Zeolita A sintetizada a partir de rejeitos do processo de beneficiamento de caulim

Energy Technology Data Exchange (ETDEWEB)

Santana, D.L.; Neves, R.F.; Silva, D.L., E-mail: danielaliraeq@yahoo.com.br, E-mail: dasilva@ufpa.br [Programa de Pos-Graduacao em Engenharia Quimica, Universidade Federal do Para - UFPA, Belem, PA (Brazil); Saraiva, A.C.F. [Centro de Tecnologia da Eletronorte, Belem, PA (Brazil)

2012-04-15

Raw materials were used to synthesize zeolite A as an alternative and more economical source of silica and aluminum, using waste from the kaolin of the paper industry. Zeolites are crystalline substances with a structure characterized by a framework of linked tetrahedra, each one consisting of four oxygen atoms surrounding a cation. The development of processes for the synthesis of zeolites is of great interest for use in the areas of purification, adsorption and catalysis. The starting materials for the synthesis of zeolite A consisted of wastes from kaolin beneficiation of paper companies of Para state, Brazil. The zeolite was obtained after calcination at 85 and 110 deg C during 24 h. The characterization of the starting material was performed by X-ray diffraction, chemical analysis, thermogravimetric and differential thermal analysis, and scanning electron microscopy. The characterization of zeolite A was done by X-ray diffraction and scanning electron microscopy. The kaolin waste used as starting material showed to be essentially kaolinite mineral. For the temperatures and time used in the synthesis it was possible to form the crystalline phase of zeolite A for the two starting materials. (author)

Chemical Decontamination of Metallic Waste from Uranium Conversion Plant Dismantling

International Nuclear Information System (INIS)

Hwang, D. S.; Choi, Y. D.; Hwang, S. T.; Park, J. H.; Byun, J. I.; Jang, N. S.

2005-01-01

Korea Atomic Energy Research Institute (KAERI) started a decommissioning program of the uranium conversion plant. Pre-work was carried as follows; installation of the access control facility, installation of a changing room and shower room, designation of an emergency exit way and indicating signs, installation of a radiation management facility, preparation of a storage area for tools and equipments, inspection and load test of crane, distribution and packaging of existing waste, and pre-decontamination of the equipment surface and the interior. First, decommissioning work was performed in kiln room, which will be used for temporary radioactive waste storage room. Kiln room housed hydro fluorination rotary kiln for production of uranium tetra-fluoride. The kiln is about 0.8 m in diameter and 5.5 m long. The total dismantled waste was 6,690 kg, 73 % of which was metallic waste and 27 % the others such as cable, asbestos, concrete, secondary waste, etc. And effluent treatment room and filtration room were dismantled for installation of decontamination equipment and lagoon sludge treatment equipment. There were tanks and square mixer in these rooms. The total dismantled waste was 17,250 kg, 67% of which was metallic waste and 33% the others. These dismantled metallic wastes consist of stainless and carbon steel. In this paper, the stainless steel plate and pipe were decontaminated by the chemical decontamination with ultrasonic

Synthesis of microporous material faujasite-type from kaolin waste

International Nuclear Information System (INIS)

Hildebrando, E.A.; Valenzuela-Diaz, F.R.; Angelica, R.S.; Neves, R.F.

2010-01-01

Zeolite with structure faujasite was synthesized using kaolin waste from kaolin processing industries for paper coating as predominant source of silicon and aluminum; the starting material was characterized by XRF, XRD, DTA/TG, SEM, and products obtained by XRD and SEM. Synthesis in hydrothermal conditions occurred on autoclave and time-temperature effects, as well as the relationship Si/Al were considered. The results show that the methodology developed with the waste of calcined kaolin reacting at 90 deg C for 20 hours in an alkaline medium, in the presence of an additional source of silica was obtained zeolite Y as single phase present in the product. (author)

The incineration of solid radioactive waste: a centralized solution

International Nuclear Information System (INIS)

Hernborg, G.; Broden, K.; Oehrn, G.

1985-01-01

Almost all the combustible low-level β- and γ-radioactive waste from Sweden, and even some waste from German nuclear power plants, is treated in an incineration plant at Studsvik. To date most of the ash has been put into 100-litre drums, which in turn have been put in 200-litre drums with concrete in between. Recently, methods have been developed and equipment installed for homogeneous solidification of the ash into concrete. Over the years since the start-up of the plant in 1976 the incinerator has worked with a high availability factor. Personnel doses and activity releases to the environment are well below limits set by regulatory authorities. (orig.)

Biochemical methane potential (BMP) of artichoke waste: the inoculum effect.

Science.gov (United States)

Fabbri, Andrea; Serranti, Silvia; Bonifazi, Giuseppe

2014-03-01

The aim of this work was to investigate anaerobic digestibility of artichoke waste resulting from industrial transformation. A series of batch anaerobic digestion tests was performed in order to evaluate the biochemical methane potential of the matrix in respect of the process. A comparison of the different performances of the laboratory-scale reactors operating in mesophilic conditions and utilizing three different values of the inoculum/substrate ratio was carried out. The best performance was achieved with an inoculum/substrate ratio of 2. Artichoke-processing byproducts showed a classical organic waste decomposition behaviour: a fast start-up phase, an acclimation stage, and a final stabilization phase. Following this approach, artichoke waste reached chemical oxygen demand removal of about 90% in 40 days. The high methane yield (average 408.62 mL CH4 gvs (-1) voltatile solids), makes artichoke waste a good product to be utilized in anaerobic digestion plants for biogas production.

Independent engineering review of the Hanford Waste Vitrification System

International Nuclear Information System (INIS)

1991-10-01

The Hanford Waste Vitrification Plant (HWVP) was initiated in June 1987. The HWVP is an essential element of the plan to end present interim storage practices for defense wastes and to provide for permanent disposal. The project start was justified, in part, on efficient technology and design information transfer from the prototype Defense Waste Processing Facility (DWPF). Development of other serial Hanford Waste Vitrification System (HWVS) elements, such as the waste retrieval system for the double-shell tanks (DSTs), and the pretreatment system to reduce the waste volume converted into glass, also was required to accomplish permanent waste disposal. In July 1991, at the time of this review, the HWVP was in the Title 2 design phase. The objective of this technical assessment is to determine whether the status of the technology development and engineering practice is sufficient to provide reasonable assurance that the HWVP and the balance of the HWVS system will operate in an efficient and cost-effective manner. The criteria used to facilitate a judgment of potential successful operation are: vitrification of high-level radioactive waste from specified DSTs on a reasonably continuous basis; and glass produced with physical and chemical properties formally acknowledge as being acceptable for disposal in a repository for high-level radioactive waste. The criteria were proposed specifically for the Independent Engineering Review to focus that assessment effort. They are not represented as the criteria by which the Department will judge the prudence of the Project. 78 refs., 10 figs., 12 tabs

Independent engineering review of the Hanford Waste Vitrification System

Energy Technology Data Exchange (ETDEWEB)

1991-10-01

The Hanford Waste Vitrification Plant (HWVP) was initiated in June 1987. The HWVP is an essential element of the plan to end present interim storage practices for defense wastes and to provide for permanent disposal. The project start was justified, in part, on efficient technology and design information transfer from the prototype Defense Waste Processing Facility (DWPF). Development of other serial Hanford Waste Vitrification System (HWVS) elements, such as the waste retrieval system for the double-shell tanks (DSTs), and the pretreatment system to reduce the waste volume converted into glass, also was required to accomplish permanent waste disposal. In July 1991, at the time of this review, the HWVP was in the Title 2 design phase. The objective of this technical assessment is to determine whether the status of the technology development and engineering practice is sufficient to provide reasonable assurance that the HWVP and the balance of the HWVS system will operate in an efficient and cost-effective manner. The criteria used to facilitate a judgment of potential successful operation are: vitrification of high-level radioactive waste from specified DSTs on a reasonably continuous basis; and glass produced with physical and chemical properties formally acknowledge as being acceptable for disposal in a repository for high-level radioactive waste. The criteria were proposed specifically for the Independent Engineering Review to focus that assessment effort. They are not represented as the criteria by which the Department will judge the prudence of the Project. 78 refs., 10 figs., 12 tabs.

Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste, April--June 1978

International Nuclear Information System (INIS)

Herald, W.R.; Roberts, R.C.

1978-01-01

A series of runs was performed in which waste processing facility influent was spiked with americium-241, neptunium-237, and uranium-233 and run through the ultrafiltration and reverse osmosis (RO) units. The results of these experiments show that the ultrafiltration membranes are ionic dependent, whereas the RO unit is not. Membrane irradiation studies have been started. Continuous run parameters are being verified through a series of experiments. The small laboratory column tests were continued this quarter on several adsorbents. Decontamination factors were calculated for these adsorbents in removing neptunium-237 and americium-241 from waste solutions. Tests were continued with the 2-in. Engineering Columns using ultrafiltration product spiked with uranium-233. A 6-in. diameter column was installed in the combined raffinate line from the three Engineering Columns. This ''mixed bed'' column will polish the waste solution that is returned to the waste processing facility tanks. A quality control program was started this quarter

Progress and future direction for the interim safe storage and disposal of Hanford high level waste (HLW)

International Nuclear Information System (INIS)

Wodrich, D.D.

1996-01-01

This paper describes the progress made at the largest environmental cleanup program in the United States. Substantial advances in methods to start interim safe storage of Hanford Site high-level wastes, waste characterization to support both safety- and disposal-related information needs, and proceeding with cost-effective disposal by the US DOE and its Hanford Site contractors, have been realized. Challenges facing the Tank Waste Remediation System Program, which is charged with the dual and parallel missions of interim safe storage and disposal of the high-level tank waste stored at the Hanford Site, are described

School Starting Age and Crime

DEFF Research Database (Denmark)

Landersø, Rasmus; Nielsen, Helena Skyt; Simonsen, Marianne

This paper investigates the effects of school starting age on crime while relying on variation in school starting age induced by administrative rules; we exploit that Danish children typically start first grade in the calendar year they turn seven, which gives rise to a discontinuity in children......’s school starting age. Analyses are carried out using register-based Danish data. We find that higher age at school start lowers the propensity to commit crime, but that this reduction is caused by incapacitation while human capital accumulation is unaffected. Importantly, we also find that the individuals...

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

Co-composting of eggshell waste in self-heating reactors: monitoring and end product quality

OpenAIRE

Soares, Micaela A. R.; Quina, Margarida M. J.; Quinta-Ferreira, Rosa M.

2013-01-01

Industrial eggshell waste (ES) is classified as an animal by-product not intended to human consumption. For reducing pathogen spreading risk due to soil incorporation of ES, sanitation by composting is a pre-treatment option. This work aims to evaluate eggshell waste recycling in self-heating composting reactors and investigate ES effect on process evolution and end product quality. Potato peel, grass clippings and rice husks were the starting organic materials considered. The incorporati...

French surface disposal experience. The disposal of large waste

International Nuclear Information System (INIS)

Dutzer, Michel; Lecoq, Pascal; Duret, Franck; Mandoki, Robert

2006-01-01

delivered at the end of June 2005 and the 55 vessel heads should be disposed by 2013. The safety approach of the facility was adapted to take into account the disposal of such large waste. This methodology and the disposal technique can be generalised to receive large waste from decommissioning activities for which cutting works and conditioning in standard packages would not be relevant. For instance this option is investigated for steam generators and could be helpful to manage waste from the important decommissioning program that is starting up in France in particular for the first generation power reactors. This decommissioning program also motivated the implementation of a facility for the disposal very low level waste, in agreement with French regulation for the management of waste in nuclear facilities. It is located in Morvilliers village, close to Centre de l'Aube facility. Disposal is performed in trenches in clay that are protected from rainwater by removable roofs. Standard packages were developed even if handling techniques are more 'rustic' due to very low dose rate. First deliveries were done in October 2003. Since start up large waste, as concrete blocks or heat exchangers, have been disposed. For very heavy waste, the interest of dedicated disposal cells is investigated. (authors)

Nuclear waste. DOE's program to prepare high-level radioactive waste for final disposal

International Nuclear Information System (INIS)

Bannerman, Carl J.; Owens, Ronald M.; Dowd, Leonard L.; Herndobler, Christopher S.; Purvine, Nancy R.; Stenersen, Stanley G.

1989-11-01

In summary, as of December 1988, the four sites collectively stored about 95 million gallons of high-level waste in underground tanks and bins. Approximately 57 million gallons are stored at Hanford, 34 million gallons at Savannah River, 3 million gallons at INEL, and 6 million gallons at West Valley. The waste is in several forms, including liquid, sludge, and dry granular materials, that make it unsuitable for permanent storage in its current state at these locations. Leaks from the tanks, designed for temporary storage, can pose an environmental hazard to surrounding land and water for thousands of years. DOE expects that when its waste processes at Savannah River, West Valley, and Hanford become operational, the high-level radioactive waste stored at these sites will be blended with other materials to immobilize it by forming a glass-like substance. The glass form will minimize the risk of environmental damage and make the waste more acceptable for permanent disposal in a geologic repository. At INEL, DOE is still considering various other immobilization and permanent disposal approaches. In July 1989, DOE estimated that it would cost about $13 billion (in fiscal year 1988 dollars) to retrieve, process, immobilize, and store the high-level waste until it can be moved to a permanent disposal site: about $5.3 billion is expected to be spent at Savannah River, $0.9 billion at West Valley, $2.8 billion at Hanford, and $4.0 billion at INEL. DOE has started construction at Savannah River and West Valley for facilities that will be used to transform the waste into glass (a process known as vitrification). These sites have each encountered schedule delays, and one has encountered a significant cost increase over earlier estimates. More specifically, the Savannah River facility is scheduled to begin high-level waste vitrification in 1992; the West Valley project, based on a January 1989 estimate, is scheduled to begin high-level waste vitrification in 1996, about 8

Derivation of Waste Acceptance Criteria for Low and Intermediate Level Waste in Surface Disposal Facility

International Nuclear Information System (INIS)

Gagner, L.; Voinis, S.

2000-01-01

In France, low- and intermediate-level radioactive wastes are disposed in a near-surface facility, at Centre de l'Aube disposal facility. This facility, which was commissioned in 1992, has a disposal capacity of one million cubic meters, and will be operated up to about 2050. It took over the job from Centre de la Manche, which was commissioned in 1969 and shut down in 1994, after having received about 520,000 cubic meters of wastes. The Centre de l'Aube disposal facility is designed to receive a many types of waste produced by nuclear power plants, reprocessing, decommissioning, as well as by the industry, hospitals and armed forces. The limitation of radioactive transfer to man and the limitation of personnel exposure in all situations considered plausible require limiting the total activity of the waste disposed in the facility as well as the activity of each package. The paper presents how ANDRA has derived the activity-related acceptance criteria, based on the safety analysis. In the French methodology, activity is considered as end-point for deriving the concentration limits per package, whereas it is the starting point for deriving the total activity limits. For the concentration limits (called here LMA) the approach consists of five steps: the determination of radionuclides important for safety with regards to operational and long-term safety, the use of relevant safety scenarios as a tool to derive quantitative limits, the setting of dose constraint per situation associated with scenarios, the setting of contribution factor per radionuclide, and the calculation of concentration activity limits. An exhaustive survey has been performed and has shown that the totality of waste packages which should be delivered by waste generators are acceptable in terms of activity limits in the Centre de l'Aube. Examples of concentration activity limits derived from this methodology are presented. Furthermore those limits have been accepted by the French regulatory body and

Acceptance of non-fuel assembly hardware by the Federal Waste Management System

International Nuclear Information System (INIS)

1990-03-01

This report is one of a series of eight prepared by E. R. Johnson Associates, Inc. (JAI) under ORNL's contract with DOE's OCRWM Systems Integration Program and in support of the Annual Capacity Report (ACR) Issue Resolution Process. The report topics relate specifically to the list of high-priority technical waste acceptance issues developed jointly by DOE and a utility-working group. JAI performed various analyses and studies on each topic to serve as starting points for further discussion and analysis leading eventually to finalizing the process by which DOE will accept spent fuel and waste into its waste management system. The eight reports are concerned with the conditions under which spent fuel and high-level waste will be accepted in the following categories: failed fuel; consolidated fuel and associated structural parts; non-fuel-assembly hardware; fuel in metal storage casks; fuel in multi-element sealed canisters; inspection and testing requirements for wastes; canister criteria; spent fuel selection for delivery; and defense and commercial high-level waste packages. 14 refs., 12 figs., 43 tabs

On the effectiveness in implementing a waste-management-plan method in construction

International Nuclear Information System (INIS)

Tam, Vivian W.Y.

2008-01-01

The increasing awareness of waste management concerns from construction and demolition waste has led to the development of waste management as an important function of construction project management. The Hong Kong government started employing the implementation of a waste-management-plan (WMP) method for all construction projects in 2003. During the trial period, the government received different version of feedback from the industry. It also came out that detailed descriptions of waste management procedures in the WMP method largely affect the productivity of companies. This paper investigates the effectiveness of the existing implementation of the WMP method in the Hong Kong construction industry. A questionnaire survey and structured interviews were conducted. The result showed that 'Propose methods for on-site reuse of materials' and 'Propose methods for reducing waste' are the main benefits gained from the implementation of the WMP method. However, 'Low financial incentive' and 'Increase in overhead cost' are considered as the major difficulties in the implementation. From that, 'Use of prefabricated building components' is considered as the major effective measure to encourage the implementation of the WMP method

Finnish Research Programme on Nuclear Waste Management (KYT). Framework Programme for 2002-2005

International Nuclear Information System (INIS)

Rasilainen, K.

2002-12-01

The new Finnish research programme on nuclear waste management (KYT) will be conducted in 2002 - 2005. This framework programme describes the starting point, the basic aims and the organisation of the research programme. The starting point of the KYT programme is derived from the present state and future challenges of Finnish nuclear waste management. The research programme is funded mainly by the Ministry of Trade and Industry (KTM), the Radiation and Nuclear Safety Authority (STUK), Posiva Oy, Fortum Oyj, Teollisuuden Voima Oy (TVO), and the National Technology Agency (Tekes). As both regulators and implementors are involved, the research programme concentrates on neutral research topics that must be studied in any case. Methods and tools for experimental and theoretical studies fall in this category. State of the art -reviews on relevant topics also create national know-how. Topics that directly belong to licensing activities of nuclear waste management are excluded from the research programme. KYT carries out technical studies that increase national know-how in the area of nuclear waste management. The aim is to maintain and develop basic expertise needed in the operations derived from the national nuclear waste management plan. The studies have been divided into strategic studies and studies enhancing the long-term safety of spent nuclear fuel disposal. Strategic studies support the overall feasibility of Finnish nuclear waste management. These studies include basic options and overall safety principles related to nuclear fuel cycle and nuclear waste management. In addition, general cost estimates as well as general safety considerations related to transportations, low- and medium level wastes, and decommissioning are included in strategic studies. Studies supporting the long-term safety of spent fuel disposal include issues related to performance assessment methodology, release of radionuclides from the repository, behaviour of bedrock and groundwater

Reconstruction and modernization of Novi Han radioactive waste repository

International Nuclear Information System (INIS)

Kolev, I.; Dralchev, D.; Spasov, P.; Jordanov, M.

2000-01-01

This report presents briefly the most important issues of the study performed by EQE - Bulgaria. The objectives of the study are the development of conceptual solutions for construction of the following facilities in the Novi Han radioactive waste repository: an operational storage for unconditioned high level spent sources; new temporary buildings over the existing radioactive waste storage facilities; a rain-water draining system ect. The study also includes the engineering solutions for conservation of the existing facilities, currently full with high level spent sources. A 'Program for reconstruction and modernization' has been created, including the analysis of some regulation aspects concerning this program implementation. In conclusions the engineering problems of Novi Han repository are clear and appropriate solutions are available. They can be implemented in both cases of 'small' or 'large' reconstruction. The reconstruction project anyway should start with the construction of a new site infrastructure. Reconstruction and modernization of Novi Han radioactive waste repository is the only way to improve the management and safety of radioactive waste from medicine, industry and scientific research in Bulgaria

Morbidity, including fatal morbidity, throughout life in men entering adult life as obese

DEFF Research Database (Denmark)

Zimmermann, Esther; Holst, Claus; Sørensen, Thorkild I A

2011-01-01

The association between obesity in adults and excess morbidity and mortality is well established, but the health impact throughout adult life of being obese in early adulthood needs elucidation. We investigated somatic morbidity, including fatal morbidity, throughout adulthood in men starting adult...... life as obese....

Radioactive waste repository of high ecological safety

International Nuclear Information System (INIS)

Sobolev, I.; Barinov, A.; Prozorov, L.

2000-01-01

With the purpose to construct a radioactive waste repository of high ecological safety and reliable containment, MosNPO 'Radon' specialists have developed an advanced type repository - large diameter well (LBD) one. A project is started for the development of a technology for LDW repository construction and pilot operation of the new repository for 25-30 years. The 2 LDW repositories constructed at the 'Radon' site and the developed monitoring system are described

Bench-scale arc melter for R ampersand D in thermal treatment of mixed wastes

International Nuclear Information System (INIS)

Kong, P.C.; Grandy, J.D.; Watkins, A.D.; Eddy, T.L.; Anderson, G.L.

1993-05-01

A small dc arc melter was designed and constructed to run bench-scale investigations on various aspects of development for high-temperature (1,500-1,800 degrees C) processing of simulated transuranic-contaminated waste and soil located at the Radioactive Waste Management Complex (RWMC). Several recent system design and treatment studies have shown that high-temperature melting is the preferred treatment. The small arc melter is needed to establish techniques and procedures (with surrogates) prior to using a similar melter with the transuranic-contaminated wastes in appropriate facilities at the site. This report documents the design and construction, starting and heating procedures, and tests evaluating the melter's ability to process several waste types stored at the RWMC. It is found that a thin graphite strip provides reliable starting with initial high current capability for partially melting the soil/waste mixture. The heating procedure includes (1) the initial high current-low voltage mode, (2) a low current-high voltage mode that commences after some slag has formed and arcing dominates over the receding graphite conduction path, and (3) a predominantly Joule heating mode during which the current can be increased within the limits to maintain relatively quiescent operation. Several experiments involving the melting of simulated wastes are discussed. Energy balance, slag temperature, and electrode wear measurements are presented. Recommendations for further refinements to enhance its processing capabilities are identified. Future studies anticipated with the arc melter include waste form processing development; dissolution, retention, volatilization, and collection for transuranic and low-level radionuclides, as well as high vapor pressure metals; electrode material development to minimize corrosion and erosion; refractory corrosion and/or skull formation effects; crucible or melter geometry; metal oxidation; and melt reduction/oxidation (redox) conditions

Double stage dry-wet-fermentation - start-up of a pilot biogas plant

International Nuclear Information System (INIS)

Buschmann, Jeannette; Busch, Gunter; Burkhardt, Marko

2009-01-01

The Brandenburg University of Technology (BTU) has developed a double stage dry-wet fermentation process for fast and safe anaerobic degradation. Originally designed for treatment of organic wastes, this process allows using a wide variety of solid biodegradable materials. The dividing of hydrolysis and methanation in this process, allows an optimization of the different steps of biogas generation separately. The main advantages of the process are the optimum process control, an extremely stable process operation and a high gas productivity and quality. Compared to conventional processes, the retention times within the percolation stage (hydrolysis) are reduced considerably. In cooperation with the engineering and consulting company GICON, the technology was qualified further to an industrial scale. In 2007 a pilot plant, and, simultaneously, an industrial plant were built by GICON based on this double stage technology. Based on practical experience from the operation of laboratory fermentation plants, the commissioning of the pilot plant was planned, controlled and monitored by our institution. The start-up of a biogas plant of this type focuses mainly on the inoculation the of methane reactor. The growth of microbial populations and generation of a stable biocenosis within the methane reactor is essential and affects the duration of starting period as well as the methanation efficiency a long time afterwards. This paper concerns with start-up of a pilot biogas plant and discusses particular occurrences and effects during this period. (author)

Waste processing by pyrolysis; Posibilidades de la pirolisis en el tratamiento de los residuos

Energy Technology Data Exchange (ETDEWEB)

Elias, X.

2002-07-01

The present work starts reminding the beginnings of pyrolysis and its applications. Nevertheless the Directive 2000/76/CE talks about it and gasification calling them intermediate systems for waste to energy. Of all it, the conclusions is that both gasification and particularly pyrolysis alone cannot solve the environmental challenges that the treatment of the present waste supposes. Thus it is precise to refer to a larger set of technologies. Of the industrial applications it is inferred that both gasification and pyrolysis generate a minimum amount of gases, in comparison with the conventional incineration, so they are more advanced technologies of treatment. Pyrolysis allows a larger treatment of waste because, depending on an organic/inorganic relation present in the waste, provides a better fitting to the treatment. (Author)

Mochovce waste treatment centre

International Nuclear Information System (INIS)

Sedliak, D.; Endrody, J.

2000-01-01

The first unit of the Mochovce NPP (WWER 440 MW) was put in a test operation in October 1998. The second unit with the same power output was put in the test operation in March 2000. The Nuclear Regulatory Authority of the Slovak Republic in its Decision No. 318/98 of 28 October 1998, by which an agreement with the operation of the Unit 1 of the Mochovce. Nuclear Power Plant was issued, requires to start the construction of the Liquid Radioactive Waste Treatment Centre until January 2004. The subject of this presentation is a system description of the Liquid Radioactive Waste (LRW) management in the Mochovce NPP. The initial part is dedicated to a short description of the radioactive waste management legislation requirements. Then the presentation continues with an information about the LRW production in the Mochovce NPP, LRW sources, chemical and radiochemical attributes, description of storage. The presentation also provides real values of its production in a comparison with the design data. The LRW production minimization principles are also mentioned there. Another part deals with the basic requirements for the technology proposal of the liquid RW treatment, especially concerning the acceptance criteria at the Republic RW Repository Mochovce. The final part is devoted to a short description of the investment procedure principles - design preparation levels and a proposed construction schedule of the centre. (authors)

High-level radioactive waste in Canada. Background paper

International Nuclear Information System (INIS)

Fawcett, R.

1993-11-01

The disposal of radioactive waste is one of the most challenging environmental problems facing Canada today. Since the Second World War, when Canadian scientists first started to investigate nuclear reactions, there has been a steady accumulation of such waste. Research reactors built in the early postwar years produced small amounts of radioactive material but the volume grew steadily as the nuclear power reactors constructed during the 1960s and 1970s began to spawn used fuel bundles. Although this radioactive refuse has been safely stored for the short term, no permanent disposal system has yet been fully developed and implemented. Canada is not alone in this regard. A large number of countries use nuclear power reactors but none has yet put in place a method for the long-term disposal of the radioactive waste. Scientists and engineers throughout the world are investigating different possibilities; however, enormous difficulties remain. In Canada, used fuel bundles from nuclear reactors are defined as high-level waste; all other waste created at different stages in the nuclear fuel cycle is classified as low-level. Although disposal of low-level waste is an important issue, it is a more tractable problem than the disposal of high-level waste, on which this paper will concentrate. The paper discusses the nuclear fuel waste management program in Canada, where a long-term disposal plan has been under development by scientists and engineers over the past 15 years, but will not be completed for some time. Also discussed are responses to the program by parliamentary committees and aboriginal and environmental groups, and the work in the area being conducted in other countries. (author). 1 tab

High-level radioactive waste in Canada. Background paper

Energy Technology Data Exchange (ETDEWEB)

Fawcett, R [Library of Parliament, Ottawa, ON (Canada). Science and Technology Div.

1993-11-01

The disposal of radioactive waste is one of the most challenging environmental problems facing Canada today. Since the Second World War, when Canadian scientists first started to investigate nuclear reactions, there has been a steady accumulation of such waste. Research reactors built in the early postwar years produced small amounts of radioactive material but the volume grew steadily as the nuclear power reactors constructed during the 1960s and 1970s began to spawn used fuel bundles. Although this radioactive refuse has been safely stored for the short term, no permanent disposal system has yet been fully developed and implemented. Canada is not alone in this regard. A large number of countries use nuclear power reactors but none has yet put in place a method for the long-term disposal of the radioactive waste. Scientists and engineers throughout the world are investigating different possibilities; however, enormous difficulties remain. In Canada, used fuel bundles from nuclear reactors are defined as high-level waste; all other waste created at different stages in the nuclear fuel cycle is classified as low-level. Although disposal of low-level waste is an important issue, it is a more tractable problem than the disposal of high-level waste, on which this paper will concentrate. The paper discusses the nuclear fuel waste management program in Canada, where a long-term disposal plan has been under development by scientists and engineers over the past 15 years, but will not be completed for some time. Also discussed are responses to the program by parliamentary committees and aboriginal and environmental groups, and the work in the area being conducted in other countries. (author). 1 tab.

Global Trends in CD4 Cell Count at the Start of Antiretroviral Therapy: Collaborative Study of Treatment Programs

NARCIS (Netherlands)

Anderegg, Nanina; Panayidou, Klea; Abo, Yao; Alejos, Belen; Althoff, Keri N.; Anastos, Kathryn; Antinori, Andrea; Balestre, Eric; Becquet, Renaud; Castagna, Antonella; Castelnuovo, Barbara; Chêne, Geneviève; Coelho, Lara; Collins, Intira Jeannie; Costagliola, Dominique; Crabtree-Ramírez, Brenda; Dabis, Francois; D'Arminio Monforte, Antonella; Davies, Mary-Ann; de Wit, Stéphane; Delpech, Valérie; de La Mata, Nicole L.; Duda, Stephany; Freeman, Aimee; Gange, Stephen J.; Grabmeier-Pfistershammer, Katharina; Gunsenheimer-Bartmeyer, Barbara; Jiamsakul, Awachana; Kitahata, Mari M.; Law, Matthew; Manzardo, Christian; McGowan, Catherine; Meyer, Laurence; Moore, Richard; Mussini, Cristina; Nakigoz, Gertrude; Nash, Denis; tek Ng, Oon; Obel, Niels; Pantazis, Nikos; Poda, Armel; Raben, Dorthe; Reiss, Peter; Riggen, Larry; Sabin, Caroline; d'Amour Sinayobye, Jean; Sönnerborg, Anders; Stoeckle, Marcel; Thorne, Claire; Torti, Carlo

2018-01-01

Early initiation of combination antiretroviral therapy (cART), at higher CD4 cell counts, prevents disease progression and reduces sexual transmission of human immunodeficiency virus (HIV). We describe the temporal trends in CD4 cell counts at the start of cART in adults from low-income,

Performance Evaluation of the Effect of waste paper on Groundnut Shell Briquette

Directory of Open Access Journals (Sweden)

Olatunde A Oyelaran

2015-07-01

Full Text Available Current energy shortage and environmental issues resulting from the use of fossil fuels have lead to exploitation of renewable energy resources that includes municipal waste and agricultural residues. These residues are available, indigenous and are environmental friendly but some can not be used directly in combustion process due high moisture content and low volumetric energy unless by briquetting. The study was undertaken to assess the combustion characteristic of binderless briquettes produced from waste paper and groundnut shell. Combustion characteristics investigated were ignition time, burning time, calorific values, burning rate, specific fuel consumption, fuel efficiency and water boiling time. The calorific values of the briquettes ranged from 19.51 - 19.92 MJ/kg, while the thermal efficiency ranges between 13.75 – 21.64%, other results shows that the average burning rate between 0.511 and 1.133 kg/hr and the specific fuel consumption ranges between 0.087 and 0.131 J/g. The recorded boiling time values were between 17.5 and 30.0 minutes for cold start and 15.0 and 20.0 minutes for hot start. The results shows that waste paper and groundnut shell up to 25% in composition composite briquettes were found to have good combustion characteristics which qualify them as alternative to firewood for domestic and industrial energy. However, production of briquettes from waste paper and groundnut shell at mixing ratio of 85:15 was found to comparatively better from all experiment conducted.

Biodegradation of an oily bilge waste using algae

Energy Technology Data Exchange (ETDEWEB)

Carpenter, M.J.

1987-01-01

A mixed community of microogranisms was collected from the harbor at the North Island Navy Base and was monitored in a test ecosystem containing an oily bilge waste obtained from off-loading ships. Cultures were examined in the presence and absence of the algae. It was thought that the algae might enhance the degradation of the oil waste by providing oxygen and possibly a nutrient source from dying phytoplankton for the bacterial community. The change in community structure was monitored by isolating the various groups of organisms and determining the biomass change over time for the algae, bacteria and yeasts/fungi subjected to the bilge waste. The biomass (i.e., colony forming units) of the yeasts and fungi increased 100 fold in a 6 week test period. The community containing only the bacteria and fungi/yeasts lost the fungal component of the population, although active bacteria biomass increased more than 10 fold during exposure to the waste. The test ecosystem was subjected to a radiolabeled compound (/sup 14/C-phenol) and bilge waste mixture to ascertain the ability of the communities to mineralize the phenol and/or assimilate the labeled hydrocarbon. The community containing the algae started mineralizing the phenol (measure by /sup 14/CO/sub 2/ production) 24 hours after exposure to the waste/phenol mixture. The bacteria/yeast-fungi community had a lag period of 384 hours before extensive catabolism of the labeled compound occurred. Current data indicate algae may enhance the biodegradation rate of oil bilge waste in a mixed microbial community.

Anaerobic digestion of cellulosic wastes

International Nuclear Information System (INIS)

Lee, D.D.; Donaldson, T.L.

1985-01-01

Anaerobic digestion is a potentially attractive technology for volume reduction of low-level radioactive cellulosic wastes. A substantial fraction of the waste is converted to off-gas and a relatively small volume of biologically stabilized sludge is produced. Process development work has been completed using a 75-L digester to verify rates and conversions obtained at the bench scale. Start-up and operating procedures have been developed, and effluent was generated for characterization and disposal studies. Three runs using batch and fed-batch conditions were made lasting 36, 90, and 423 d. Solids solubilization rates and gas production rates averaged approximately 1.8 g cellulose per L of reactor per d and 1.2 L of off-gas per L reactor per d. Greater than 80% destruction of the volatile suspended solids was obtained. A simple dynamic process model was constructed to aid in process design and for use in process monitoring and control of a large-scale digester

Factor of radioactive waste on nuclear power program

International Nuclear Information System (INIS)

Syed Abdul Malik Syed Zain

2009-01-01

Global warming phenomena and rising oil prices have brought the excitement of open space use of nuclear power. Arguments in favor of this technology range in terms of more environmentally friendly, energy diversification and cost efficiency has prompted the government to widen the choice of nuclear power be considered as a serious alternative. Despite the attractive factors to the use of these powers, there are also factors that stem from the continued development of nuclear power. These include the factor of safety, security, security of fuel supply, and public attention is often associated with radioactive waste management. This article attempts to debate specific to radioactive waste management factors that impact on public acceptance of a country's nuclear power program, especially in Malaysia. Starting from the absence of radioactive waste management policy to model uncertainty of the landfill and complications in selecting a repository site shows the basic infrastructure is still lacking. In addition, previous experience handling thorium waste has not reached a final settlement after several years of implementation. It reinforced the perception about the level of public confidence in the competence and attitude of local workers who are not very encouraging to pursue this advanced.

Organic tanks safety program waste aging studies. Final report, Revision 1

Energy Technology Data Exchange (ETDEWEB)

Camaioni, D.M.; Samuels, W.D.; Linehan, J.C. [and others

1998-09-01

Uranium and plutonium production at the Hanford Site produced large quantities of radioactive byproducts and contaminated process chemicals that are stored in underground tanks awaiting treatment and disposal. Having been made strongly alkaline and then subjected to successive water evaporation campaigns to increase storage capacity, the wastes now exist in the physical forms of saltcakes, metal oxide sludges, and aqueous brine solutions. Tanks that contain organic process chemicals mixed with nitrate/nitrite salt wastes might be at risk for fuel-nitrate combustion accidents. This project started in fiscal year 1993 to provide information on the chemical fate of stored organic wastes. While historical records had identified the organic compounds originally purchased and potentially present in wastes, aging experiments were needed to identify the probable degradation products and evaluate the current hazard. The determination of the rates and pathways of degradation have facilitated prediction of how the hazard changes with time and altered storage conditions. Also, the work with aged simulated waste contributed to the development of analytical methods for characterizing actual wastes. Finally, the results for simulants provide a baseline for comparing and interpreting tank characterization data.

Organic tanks safety program waste aging studies. Final report, Revision 1

International Nuclear Information System (INIS)

Camaioni, D.M.; Samuels, W.D.; Linehan, J.C.

1998-09-01

Uranium and plutonium production at the Hanford Site produced large quantities of radioactive byproducts and contaminated process chemicals that are stored in underground tanks awaiting treatment and disposal. Having been made strongly alkaline and then subjected to successive water evaporation campaigns to increase storage capacity, the wastes now exist in the physical forms of saltcakes, metal oxide sludges, and aqueous brine solutions. Tanks that contain organic process chemicals mixed with nitrate/nitrite salt wastes might be at risk for fuel-nitrate combustion accidents. This project started in fiscal year 1993 to provide information on the chemical fate of stored organic wastes. While historical records had identified the organic compounds originally purchased and potentially present in wastes, aging experiments were needed to identify the probable degradation products and evaluate the current hazard. The determination of the rates and pathways of degradation have facilitated prediction of how the hazard changes with time and altered storage conditions. Also, the work with aged simulated waste contributed to the development of analytical methods for characterizing actual wastes. Finally, the results for simulants provide a baseline for comparing and interpreting tank characterization data

US Department of Energy acceptance of commercial transuranic waste

International Nuclear Information System (INIS)

Taboas, A.L.; Bennett, W.S.; Brown, C.M.

1980-02-01

Contaminated transuranic wastes generated as a result of non-defense activities have been disposed of by shallow land burial at a commercially operated (NECO) facility located on the Hanford federal reservation, which is licensed by the State of Washington and by the NRC. About 15,000 ft 3 of commercial TRU waste have been generated each year, but generation for the next three years could triple due to decontamination and decommissioning scheduled to start in 1980. Disposal at other commercial burial sites has been precluded due to sites closing or prohibitions on acceptance of transuranic wastes. The State of Washington recently modified the NECO-Hanford operating license, effective February 29, 1980, to provide that radioactive wastes contaminated with transuranics in excess of 10 nCi/g will not be accepted for disposal. Consistent with the state policy, the NRC amended the NECO special nuclear material license so that Pu in excess of 10n Ci/g cannot be accepted after February 29, 1980. As a result, NRC requested DOE to examine the feasibility of accepting these wastes at a DOE operated site. TRU wastes accepted by the DOE would be placed in retrievable storage in accordance with DOE policy which requires retrievable storage of transuranic wastes pending final disposition in a geologic repository. DOE transuranic wastes are stored at six major DOE sites: INEL, Hanford, LASL, NTS, ORNL, and SRP. A specific site for receiving commercial TRU waste has not yet been selected. Shipments to DOE-Hanford would cause the least disruption to past practices. Commercial TRU wastes would be subject to waste form and packaging criteria established by the DOE. The waste generators would be expected to incur all applicable costs for DOE to take ownership of the waste, and provide storage, processing, and repository disposal. The 1980 charge to generators for DOE acceptance of commercial TRU waste is $147 per cubic foot

Integrated system for long-term radioactive waste management in the UK

International Nuclear Information System (INIS)

Dalton, J.; Wisbey, S.

2003-01-01

Since the failure of Nirex application to build a Rock Characterisation Facility near Sellafield in 1997, Nirex has been applying lessons learnt from that failure. Some of the issues involved are generic and relate to the process by which legitimate authority can be gained for government policy development, the structure of the nuclear industry and the behaviour of institutions. Transparency must be central to the culture of organisations attempting to win public acceptance. In the UK, the Department for Environment, Food and Rural Affairs (DEFRA) have started a consultation process - stage one completed in March 2002 - to consult about the safe management of radioactive waste. Nirex has modified its approach to long-term waste management, using a concept of phased (stepwise and reversible) geological disposal. Nirex also provides waste producers with advice on, and endorsement of, the packaging and transport of wastes. Through these examples, this paper will demonstrate how Nirex is providing an integrated approach to the long-term management of radioactive wastes in the UK. (orig.)

An overview of the mixed waste landfill integrated demonstration

International Nuclear Information System (INIS)

Williams, C.V.; Burford, T.D.

1994-01-01

Prior to May 1992, field demonstrations of characterization technologies were performed at an uncontaminated site near the Chemical Waste Landfill. In mid-1992 through summer 1993, both non-intrusive and intrusive characterization techniques were demonstrated at the Chemical Waste Landfill. Subsurface and dry barrier demonstrations were started in summer 1993 and will continue into 1995. Future plans include demonstrations of innovative drilling, characterization and long-term monitoring, and remediation techniques. Demonstrations were also scheduled in summer 1993 at the Kirtland Air Force HSWA site and will continue in 1994. The first phase of the Thermal Enhanced Vapor Extraction System (TEVES) project occurred in April 1992 when two holes were drilled and vapor extraction wells were installed at the Chemical Waste Landfill. Obtaining the engineering design and environmental permits necessary to implement this field demonstration will take until early 1994. Field demonstration of the vapor extraction system will occur in 1994

Current situation and future plans in radioactive waste management in Mexico

International Nuclear Information System (INIS)

Lopez, H.; Jimenez, M.

1992-01-01

A brief introduction is offered in this document in order to explain the importance which is given in Mexico to the safe management of radioactive wastes. The Secretaria de Energia, Minas e Industria Paraestatal is the organization responsible for this issue. Also, a brief historical background is offered so as to understand the evolution of these activities since they were originated. This background allows us to describe the present situation, which consists in a substantial change in the volume of produced radioactive wastes; in other words, before the present situation only the, nuclear wastes from the application of radioisotopes were generated whereas currently, with the starting of commercial operation of the first unit of Laguna Verde Nuclear Power Plant (LVNPP), large volumes of industrial radioactive wastes are being generated. A mention is given as well of the acquired experience during more than 20 years of waste management and of the technologies which have been applied or practiced in the use and disposal of such wastes. Finally, some general trends in relation to the future planning are indicated, which essentially consist in the siting and characterization of a site so as to, design and construct a permanent disposal facility in order to dispose the operational radioactive wastes from LVNPP

1325-N Liquid Waste Disposal Facility Supplemental Information to the Hanford Facility Contingency Plan (DOE/RL-93-75)

International Nuclear Information System (INIS)

Edens, V.G.

1998-03-01

The 1325-N Liquid Waste Disposal Facility located at the 100-N Area of the Hanford Site started receiving part of the N Reactor liquid radioactive effluent flow in 1983. In September 1985, the 1325-N Facility became the primary liquid waste disposal system for the N Reactor. The facility is located approximately 60 feet above and 2000 feet east of the shore of the Columbia River. Waste stream discharges were ceased in April 1991.Specific information on types of waste discharged to 1325-N are contained within the Part A, Form 3, Permit application of this unit

Single-phase and two-phase anaerobic digestion of fruit and vegetable waste: Comparison of start-up, reactor stability and process performance

Energy Technology Data Exchange (ETDEWEB)

Ganesh, Rangaraj [INRA, UR50, Laboratoire de Biotechnologie de l’Environnement, Avenue des Etangs, Narbonne F-11100 (France); Torrijos, Michel, E-mail: michel.torrijos@supagro.inra.fr [INRA, UR50, Laboratoire de Biotechnologie de l’Environnement, Avenue des Etangs, Narbonne F-11100 (France); Sousbie, Philippe [INRA, UR50, Laboratoire de Biotechnologie de l’Environnement, Avenue des Etangs, Narbonne F-11100 (France); Lugardon, Aurelien [Naskeo Environnment, 52 rue Paul Vaillant Couturier, F-92240 Malakoff (France); Steyer, Jean Philippe; Delgenes, Jean Philippe [INRA, UR50, Laboratoire de Biotechnologie de l’Environnement, Avenue des Etangs, Narbonne F-11100 (France)

2014-05-01

Highlights: • Single-phase and two-phase systems were compared for fruit and vegetable waste digestion. • Single-phase digestion produced a methane yield of 0.45 m{sup 3} CH{sub 4}/kg VS and 83% VS removal. • Substrate solubilization was high in acidification conditions at 7.0 kg VS/m{sup 3} d and pH 5.5–6.2. • Energy yield was lower by 33% for two-phase system compared to the single-phase system. • Simple and straight-forward operation favored single phase process over two-phase process. - Abstract: Single-phase and two-phase digestion of fruit and vegetable waste were studied to compare reactor start-up, reactor stability and performance (methane yield, volatile solids reduction and energy yield). The single-phase reactor (SPR) was a conventional reactor operated at a low loading rate (maximum of 3.5 kg VS/m{sup 3} d), while the two-phase system consisted of an acidification reactor (TPAR) and a methanogenic reactor (TPMR). The TPAR was inoculated with methanogenic sludge similar to the SPR, but was operated with step-wise increase in the loading rate and with total recirculation of reactor solids to convert it into acidification sludge. Before each feeding, part of the sludge from TPAR was centrifuged, the centrifuge liquid (solubilized products) was fed to the TPMR and centrifuged solids were recycled back to the reactor. Single-phase digestion produced a methane yield of 0.45 m{sup 3} CH{sub 4}/kg VS fed and VS removal of 83%. The TPAR shifted to acidification mode at an OLR of 10.0 kg VS/m{sup 3} d and then achieved stable performance at 7.0 kg VS/m{sup 3} d and pH 5.5–6.2, with very high substrate solubilization rate and a methane yield of 0.30 m{sup 3} CH{sub 4}/kg COD fed. The two-phase process was capable of high VS reduction, but material and energy balance showed that the single-phase process was superior in terms of volumetric methane production and energy yield by 33%. The lower energy yield of the two-phase system was due to the loss of

Single-phase and two-phase anaerobic digestion of fruit and vegetable waste: Comparison of start-up, reactor stability and process performance

International Nuclear Information System (INIS)

Ganesh, Rangaraj; Torrijos, Michel; Sousbie, Philippe; Lugardon, Aurelien; Steyer, Jean Philippe; Delgenes, Jean Philippe

2014-01-01

Highlights: • Single-phase and two-phase systems were compared for fruit and vegetable waste digestion. • Single-phase digestion produced a methane yield of 0.45 m 3 CH 4 /kg VS and 83% VS removal. • Substrate solubilization was high in acidification conditions at 7.0 kg VS/m 3 d and pH 5.5–6.2. • Energy yield was lower by 33% for two-phase system compared to the single-phase system. • Simple and straight-forward operation favored single phase process over two-phase process. - Abstract: Single-phase and two-phase digestion of fruit and vegetable waste were studied to compare reactor start-up, reactor stability and performance (methane yield, volatile solids reduction and energy yield). The single-phase reactor (SPR) was a conventional reactor operated at a low loading rate (maximum of 3.5 kg VS/m 3 d), while the two-phase system consisted of an acidification reactor (TPAR) and a methanogenic reactor (TPMR). The TPAR was inoculated with methanogenic sludge similar to the SPR, but was operated with step-wise increase in the loading rate and with total recirculation of reactor solids to convert it into acidification sludge. Before each feeding, part of the sludge from TPAR was centrifuged, the centrifuge liquid (solubilized products) was fed to the TPMR and centrifuged solids were recycled back to the reactor. Single-phase digestion produced a methane yield of 0.45 m 3 CH 4 /kg VS fed and VS removal of 83%. The TPAR shifted to acidification mode at an OLR of 10.0 kg VS/m 3 d and then achieved stable performance at 7.0 kg VS/m 3 d and pH 5.5–6.2, with very high substrate solubilization rate and a methane yield of 0.30 m 3 CH 4 /kg COD fed. The two-phase process was capable of high VS reduction, but material and energy balance showed that the single-phase process was superior in terms of volumetric methane production and energy yield by 33%. The lower energy yield of the two-phase system was due to the loss of energy during hydrolysis in the TPAR and the

Development of waste chargeback systems at the Idaho National Engineering Laboratory (INEL)

International Nuclear Information System (INIS)

Piscitella, R.R.

1996-02-01

Chargeback systems have been discussed (and cussed), tried, modified, and in some cases, successfully implemented in the DOE complex over the years. With the current emphasis on ''Doing business like a private company,'' there has been renewed interest at the Idaho National Engineering Laboratory (INEL) in implementing chargeback systems for waste management activities. The most recent activities relating to chargeback at the INEL started the summer of 1995 with direction from waste operations management to develop and pilot test a chargeback system. This paper presents the results of this effort to date

Measurement methodology for fulfilling of waste acceptance criteria for low and intermediate level radioactive waste in storages - 59016

International Nuclear Information System (INIS)

Sokcic-Kostic, M.; Langer, F.; Schultheis, R.

2012-01-01

with half life longer than Cs-137, whereas intermediate level waste is sub-classified as short lived waste and long lived waste. Long lived isotopes are mainly alpha emitters which result from contamination of the RAW by nuclear fuel material and its fission and breeding products. The sub-classification is made on base of mass specific alpha activity of the waste. Before being sent to storage the waste has to be treated. This includes volume reduction by combustion or compaction, depending on the physical properties of the waste, as well as immobilisation by grouting, saving thereby storage space and costs. After the treatment the waste is filled into packages preferably drums or containers. Before the waste is sent to the waste storage a passport is generated which includes all relevant data to show that the waste package fulfils the requirements as defined by the waste storage operating company. NUKEM Technologies has developed a large number of monitors for a radiological waste characterisation. The preferred methods are non-destructive, allowing high throughput and giving detailed information. Parameters that cannot be measured after treatment, have to be measured during the treatment process or data has to be collected from available sources like the origin of the waste or from the waste deliverer. To optimise this process NUKEM Technologies has developed a tracking system which traces the waste during treatment starting from delivery and finishing by the transportation to the final storage. (authors)

Starting an aphasia center?

Science.gov (United States)

Elman, Roberta J

2011-08-01

Starting an aphasia center can be an enormous challenge. This article provides initial issues to review and consider when deciding whether starting a new organization is right for you. Determining the need for the program in your community, the best size and possible affiliation for the organization, and available resources, as well as developing a business plan, marketing the program, and building awareness in the community, are some of the factors that are discussed. Specific examples related to starting the Aphasia Center of California are provided. © Thieme Medical Publishers.

Technology of radioactive waste management avoiding environmental disposal

International Nuclear Information System (INIS)

1964-01-01

This report considers present radioactive waste management methods and practices. In addition, present research and development activity designed to minimize discharges to the environment are noted. During its deliberations the Panel was able to define certain avenues of research and development which should be explored to enable the almost complete containment of wastes. The experience and practices at establishments, where, for geographical, geological or other reasons, discharges of radioactive material to the environment are extremely small, served as the starting point for the Panel's deliberations. Details of the experience and practice, together with the results obtained at these establishments, are summarized in Part I and described in more detail in Part II of this report. 48 refs, 89 figs, 11 tabs

Nirex plans for low and intermediate level waste

International Nuclear Information System (INIS)

Mathieson, J.

1995-01-01

Two main events have dominated Nirex's recent history: the Radioactive Waste Review and the Company's plans to build a Rock Characterisation facility at its investigation site near Sellafield in Cumbria. The outcome of the former was announced in a White Paper in July 1995. Decisions on the RCF are subject to a public inquiry starting in September 1995. Given a successful result and confirmation that the site could meet the safety target, a deep repository for intermediate and some low level waste could be available by 2011 or thereabouts. As financing of Nirex's activities is in line with the ''polluter pays'' principle, the Company is aiming to deliver a cost-effective disposal system which complies fully with the stringent safety requirements placed on it. (author)

Health and Safety in Waste Collection: Towards Evidence-Based Worker Health Surveillance

NARCIS (Netherlands)

Kuijer, P. Paul F. M.; Sluiter, Judith K.; Frings-Dresen, Monique H. W.

2010-01-01

Background Waste collectors around the world are at risk for work-related disorders and injuries. The aim of this study was to assess work demands, acute physiologic responses, illnesses, and injuries as a starting point for worker health surveillance (WHS). Methods A systematic search was performed

The waste-to-energy framework for integrated multi-waste utilization: Waste cooking oil, waste lubricating oil, and waste plastics

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)

Concussion - what to ask your doctor - adult

Science.gov (United States)

... When can I start contact sports, such as football or soccer? When can I begin skiing or ... Traumatic brain injury (adult). In: Adams JG, ed. Emergency Medicine . 2nd ed. Philadelphia, PA: Elsevier Saunders; 2013: ...

A comparison of pediatric and adult kidney donors for adult recipients.

Science.gov (United States)

Pugliese, M R; Ridolfi, L; Nanni Costa, A; Taddei, S; Venturoli, N; Petrini, F

1999-01-01

The high demand for organs for transplantation has made it necessary to consider using even the oldest and youngest of potential donors in order to increase the organ supply. In this retrospective study, the outcome of kidney transplantation using cadaveric pediatric donors was compared with that of an adult control series. Graft procurement took place in two regions of Italy (Emilia-Romagna and Piemonte) over an 11-year period. A group of pediatric donors (Actuarial patient and graft survival rates did not differ significantly between the two groups (patient survival 96% and 96% for pediatric donors versus 98% and 92% for adult donors at 1 and 5 years post-transplantation; graft survival 76% and 68% for pediatric donors versus 88% and 74% for adult donors 1 and 5 y post-transplantation). Complications were also evaluated, but no difference was found (the only exception being the creatinine level in the 5th year). Renal transplantation with cadaveric donors starting at 4 years of age gave results comparable to kidneys coming from adults. These data show that cadaveric pediatric donor kidneys may be used in adult recipients with good results. The ethical implications of the subject are extensively reviewed.

Environmental and safety problems of waste management in nuclear engineering

International Nuclear Information System (INIS)

Schwibach, J.; Jacobi, W.

1976-01-01

The environmental and safety problems which waste management in nuclear technology poses are discussed under the aspects of the disposal of radioactive waste by nuclear facilities and the safety of radioactive waste disposal. The release and global distribution of long-lived radionuclides such as tritium, Kr-85, C-14, I-129, and Pu-239 as well as the radiation exposure of the world population resulting thereof are investigated, the authors starting from a specific production rate of the nuclides released from nuclear facilities. Definitions of the terms 'dose commitment' and 'collective dose commitment' are given. Furthermore, local radiation exposure in reprocessing plants is investigated and compared with regional and global radiation exposure. A recommendation is made to take measures which would reduce the nuclides tritium, Kr-85, and C-14 in order to achieve considerably smaller collective doses. (HR/LN) [de

Reasons for starting and stopping electronic cigarette use.

Science.gov (United States)

Pepper, Jessica K; Ribisl, Kurt M; Emery, Sherry L; Brewer, Noel T

2014-10-03

The aim of our study was to explore reasons for starting and then stopping electronic cigarette (e-cigarette) use. Among a national sample of 3878 U.S. adults who reported ever trying e-cigarettes, the most common reasons for trying were curiosity (53%); because a friend or family member used, gave, or offered e-cigarettes (34%); and quitting or reducing smoking (30%). Nearly two-thirds (65%) of people who started using e-cigarettes later stopped using them. Discontinuation was more common among those whose main reason for trying was not goal-oriented (e.g., curiosity) than goal-oriented (e.g., quitting smoking) (81% vs. 45%, p reasons for stopping e-cigarette use were that respondents were just experimenting (49%), using e-cigarettes did not feel like smoking cigarettes (15%), and users did not like the taste (14%). Our results suggest there are two categories of e-cigarette users: those who try for goal-oriented reasons and typically continue using and those who try for non-goal-oriented reasons and then typically stop using. Research should distinguish e-cigarette experimenters from motivated users whose decisions to discontinue relate to the utility or experience of use. Depending on whether e-cigarettes prove to be effective smoking cessation tools or whether they deter cessation, public health programs may need distinct strategies to reach and influence different types of users.

Phenotype Presentation of Hypophosphatemic Rickets in Adults

DEFF Research Database (Denmark)

Beck-Nielsen, Signe S; Brusgaard, Klaus; Rasmussen, Lars M

2010-01-01

Hypophosphatemic rickets (HR) is a group of rare disorders caused by excessive renal phosphate wasting. The purpose of this cross-sectional study of 38 HR patients was to characterize the phenotype of adult HR patients. Moreover, skeletal and endodontic severity scores were defined to assess poss...

The safe disposal of radioactive wastes in geologic salt formations

International Nuclear Information System (INIS)

Kuehn, K.; Proske, R.

Geologic salt formations appear to be particularly suitable for final storage. Their existance alone - the salt formations in Northern Germany are more than 200 million years old - is proof of their stability and of their isolation from biological cycles. In 1967 the storage of LAW and later, in 1972, of MAW was started in the experimental storage area Asse, south-east of Braunschweig, after the necessary technical preparations had been made. In more than ten years of operation approx. 114,000 drums of slightly active and 1,298 drums of medium-active wastes were deposited without incident. Methods have been developed for filling the available caverns with wastes and salt to ensure the security of long term disposal without supervision. Tests with electric heaters for simulation of heat-generating highly active wastes confirm the good suitability of salt formations for storing these wastes. Safety analyses for the operating time as well as for the long term phase after closure of the final storage area, which among others also comprise the improbable ''greatest expected accident'', namely break through of water, are carried out and confirm the safety of ultimate storage of radioactive wastes in geological salt formations. (orig./HP) [de

Current status of radioactive waste management from nuclear applications in Korea

International Nuclear Information System (INIS)

Kwan Sik Chun

1997-01-01

Korea has been in operation of nuclear research reactor(s) since the first research reactor, TRIGA MARK-II type, started to operate in 1965. The third research reactor, HANARO, has begun to operate since 1995 while other research reactors have been shut down for their decommissioning and will be dismantled in near future. The RI application wastes have been collected and stored at the Nuclear Environment Technology Institute (NETEC) separately from the operational wastes of nuclear power plant (NPP) which are being stored at on-site storage of each NPP. 10 refs, 2 figs, 4 tabs

Management of healthcare waste: developments in Southeast Asia in the twenty-first century.

Science.gov (United States)

Kühling, Jan-Gerd; Pieper, Ute

2012-09-01

In many Southeast Asian countries, significant challenges persist with regard to the proper management and disposal of healthcare waste. The amount of healthcare waste in these countries is continuously increasing as a result of the expansion of healthcare systems and services. In the past, healthcare waste, if it was treated at all, was mainly incinerated. In the last decade more comprehensive waste management systems were developed for Southeast Asian countries and implementation started. This also included the establishment of alternative healthcare waste treatment systems. The developments in the lower-middle-income countries are of special interest, as major investments are planned. Based upon sample projects, a short overview of the current development trends in the healthcare waste sector in Laos, Indonesia and Vietnam is provided. The projects presented include: (i) Lao Peoples Democratic Republic (development of the national environmental health training system to support the introduction of environmental health standards and improvement of healthcare waste treatment in seven main hospitals by introducing steam-based treatment technologies); (ii) Indonesia (development of a provincial-level healthcare waste-management strategy for Province Nanggroe Aceh Darussalam (NAD) and introduction of an advanced waste treatment system in a tertiary level hospital in Makassar); and (iii) Vietnam (development of a healthcare waste strategy for five provinces in Vietnam and a World Bank-financed project on healthcare waste in Vietnam).

Argentine project for the final disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Palacios, E.; Ciallella, N.R.; Petraitis, E.J.

1989-01-01

From 1980 Argentina is carrying out a research program on the final disposal of high level radioactive wastes. The quantity of wastes produced will be significant in next century. However, it was decided to start with the studies well in advance in order to demonstrate that the high level wastes could be disposed in a safety way. The option of the direct disposal of irradiated fuel elements was discarded, not only by the energetic value of the plutonium, but also for ecological reasons. In fact, the presence of a total inventory of actinides in the non-processed fuel would imply a more important radiological impact than that caused if the plutonium is recycled to produce energy. The decision to solve the technological aspects connected with the elimination of high-level radioactive wastes well in advance, was made to avoid transfering the problem to future generations. This decision is based not only on technical evaluations but also on ethic premises. (Author)

Social Media: Support for Survivors and Young Adults With Cancer.

Science.gov (United States)

Walton, AnnMarie L; Albrecht, Tara A; Lux, Lauren; Judge Santacroce, Sheila

2017-10-01

Social media use is ubiquitous among young adults. Young adults with cancer must make important decisions about where, what, and how to share information on social media. Oncology nurses are in a unique position to start conversations about the risks and benefits of social media use. This column aims to review a variety of social media platforms that may be used by young adults with cancer and provide guidance to nurses on initiating open dialogue with young adults about social media usage. 
.

Economic and energy analysis about disposal interventions of waste tires produced in Calabria

International Nuclear Information System (INIS)

Florio, Gaetano; Cersosimo, Attilio.

1997-01-01

The present paper refers to an analysis aimed at researching disposal strategies, for waste tires produced in Calabria, which ensure correct disposal with regard to environmental compatibility and their evaluation in terms of material recovery and energy. The starting point has been an estimate of the quantities of potentially usable waste tires and disposal methods currently employed. It has therefore been possible to identify two specific disposal proposals for which an economic and energy evaluation has been conducted. The last part of the paper has faced the problem of plant location under consideration, with the aim of determining, for both proposal, the cost that each producer must bear to have his waste tires eliminated

Data Package for Secondary Waste Form Down-Selection-Cast Stone

International Nuclear Information System (INIS)

Serne, R. Jeffrey; Westsik, Joseph H.

2011-01-01

Available literature on Cast Stone and Saltstone was reviewed with an emphasis on determining how Cast Stone and related grout waste forms performed in relationship to various criteria that will be used to decide whether a specific type of waste form meets acceptance criteria for disposal in the Integrated Disposal Facility (IDF) at Hanford. After the critical review of the Cast Stone/Saltstone literature, we conclude that Cast Stone is a good candidate waste form for further consideration. Cast stone meets the target IDF acceptance criteria for compressive strength, no free liquids, TCLP leachate are below the UTS permissible concentrations and leach rates for Na and Tc-99 are suiteably low. The cost of starting ingredients and equipment necessary to generate Cast Stone waste forms with secondary waste streams are low and the Cast Stone dry blend formulation can be tailored to accommodate variations in liquid waste stream compositions. The database for Cast Stone short-term performance is quite extensive compared to the other three candidate waste solidification processes. The solidification of liquid wastes in Cast Stone is a mature process in comparison to the other three candidates. Successful production of Cast Stone or Saltstone has been demonstrated from lab-scale monoliths with volumes of cm3 through m3 sized blocks to 210-liter sized drums all the way to the large pours into vaults at Savannah River. To date over 9 million gallons of low activity liquid waste has been solidified and disposed in concrete vaults at Savannah River.

Data Package for Secondary Waste Form Down-Selection—Cast Stone

Energy Technology Data Exchange (ETDEWEB)

Serne, R. Jeffrey; Westsik, Joseph H.

2011-09-05

Available literature on Cast Stone and Saltstone was reviewed with an emphasis on determining how Cast Stone and related grout waste forms performed in relationship to various criteria that will be used to decide whether a specific type of waste form meets acceptance criteria for disposal in the Integrated Disposal Facility (IDF) at Hanford. After the critical review of the Cast Stone/Saltstone literature, we conclude that Cast Stone is a good candidate waste form for further consideration. Cast stone meets the target IDF acceptance criteria for compressive strength, no free liquids, TCLP leachate are below the UTS permissible concentrations and leach rates for Na and Tc-99 are suiteably low. The cost of starting ingredients and equipment necessary to generate Cast Stone waste forms with secondary waste streams are low and the Cast Stone dry blend formulation can be tailored to accommodate variations in liquid waste stream compositions. The database for Cast Stone short-term performance is quite extensive compared to the other three candidate waste solidification processes. The solidification of liquid wastes in Cast Stone is a mature process in comparison to the other three candidates. Successful production of Cast Stone or Saltstone has been demonstrated from lab-scale monoliths with volumes of cm3 through m3 sized blocks to 210-liter sized drums all the way to the large pours into vaults at Savannah River. To date over 9 million gallons of low activity liquid waste has been solidified and disposed in concrete vaults at Savannah River.

Leaching methods for conditioned radioactive waste

International Nuclear Information System (INIS)

Carpentiero, R.; Bienvenu, P.; Huebra, A. G. de la; Dale, C.; Grec, D.; Gallego, C.; Rodriguez, M.; Vanderlinden, F.; Voors, P. I.; Welbergen, J.; May, R.; Fays, J.

2005-01-01

The physico-chemical characterization of solidified, real or simulated, radioactive waste is essential in determining their long-term stability in conditions close to that which could be encountered during disposal. The evaluation or prediction of the performance of conditioned waste passes through many suitable studies and experiments, according to a documented qualification programme. In this respect the leaching test is among the first important techniques to evaluate the feasibility of a waste form and for comparing and selecting the best waste form. So the leaching behaviour of an immobilized radioactive waste is a relevant property to be studied. The objective of the present report is to collect and describe the most representative leaching methods used in international laboratories, mainly at European level, whether standard or standard-derived. In this instance the work is a summary of the Network knowledge and applications on leaching processes in order to exchange information and scientific and technical experiences in this respect. The focus is to express all the relevant parameters of the test and its field of application. all this background is the needed starting point to clarify the similarities and shortcomings of the methods used in the EN-TRAP laboratories and, subsequently, the possible equalities or differences which can be attributed to the characteristic parameters of the different type of wastes treated. In order to comprise the significance and the effects of the parameters involved in leaching phenomena, an initial discussion on leaching mechanisms and on achievable results is made in this document. The international standardised methods are summarised as being the origin for all the network leaching procedures. This work in a preliminary way represents a comparative review ordered to introduce an unique leaching procedure to be tested in an interlaboratory comparative exercise. Further the unique method would be a quick internal reference

Creative Ageing? Selfhood, Temporality and the Older Adult Learner

Science.gov (United States)

Sabeti, Shari

2015-01-01

This paper is based on a long-term ethnography of an adult creative writing class situated in a major urban art gallery in the United Kingdom. It takes the claims of one group of older adults--that creative writing made them "feel younger"--as the starting point for exploring this connection further. It places these claims broadly within…

Low-level waste disposal site selection demonstration

International Nuclear Information System (INIS)

Rogers, V.C.

1984-01-01

This paper discusses the results of recent studies undertaken at EPRI related to low-level waste disposal technology. The initial work provided an overview of the state of the art including an assessment of its influence upon transportation costs and waste form requirements. The paper discusses work done on the overall system design aspects and computer modeling of disposal site performance characteristics. The results of this analysis are presented and provide a relative ranking of the importance of disposal parameters. This allows trade-off evaluations to be made of factors important in the design of a shallow land burial facility. To help minimize the impact of a shortage of low-level radioactive waste disposal sites, EPRI is closely observing the development of bellweather projects for developing new sites. The purpose of this activity is to provide information about lessons learned in those projects in order to expedite the development of additional disposal facilities. This paper describes most of the major stems in selecting a low-level radioactive waste disposal site in Texas. It shows how the Texas Low-Level Radioactive Waste Disposal Authority started with a wide range of potential siting areas in Texas and narrowed its attention down to a few preferred sites. The parameters used to discriminate between large areas of Texas and, eventually, 50 candidate disposal sites are described, along with the steps in the process. The Texas process is compared to those described in DOE and EPRI handbooks on site selection and to pertinent NRC requirements. The paper also describes how an inventory of low-level waste specific to Texas was developed and applied in preliminary performance assessments of two candidate sites. Finally, generic closure requirements and closure operations for low-level waste facilities in arid regions are given

Study on the correlation between volatile fatty acids and gas production in dry fermentation of kitchen waste

Science.gov (United States)

Li, Qiangqiang; Ma, Yunfeng; Du, Boying; Wang, Qi; Hu, Qiongqiong; Bian, Yushan

2018-02-01

In this study, continuous kitchen waste fermentation and anaerobic digestion experiments were conducted to analyze the gas production potential, and to study the correlation between gas production rate and volatile fatty acid (VFAs) and its component concentration. During the experiment, the total solid(TS) concentration of the reaction system was increased by adding the kitchen waste, analysis of kitchen waste dry fermentation process to start, run, imbalance and imbalance after recovery and the parameters in the process of realizing the change trend and influencing factors of dry fermentation process, pH and ammonia concentration.

The need for mixed waste treatment options within the US Department of Energy

International Nuclear Information System (INIS)

McCulla, W.H.; French, D.M.

1992-01-01

The United States Department of Energy (DOE) has generated and stored significant amounts of low-level mixed wastes consisting of radioactive materials mixed with hazardous chemical substances in various forms. The DOE is in the process of beginning a cleanup of these mixed wastes at many of its facilities. Many of these waste streams had been previously disposed of by methods acceptable at the time but with the passage of very stringent laws affecting migration of hazardous components, now the disposal areas constitute remediation sites. Disposal of low level radioactive waste potentially containing hazardous materials have also fallen under land disposal restrictions and currently no mixed waste is going to low level disposal facilities. The paper will address why the DOE is just now starting to comply with environmental laws, why there is a need to find more effective and less expensive means of cleaning up wastes, how the DOE is organizing to accomplish this cleanup, and several plasma technology development efforts in the DOE Complex that show promise of meeting these needs

The need for mixed waste treatment options within the US Department of Energy

Energy Technology Data Exchange (ETDEWEB)

McCulla, W.H.; French, D.M.

1992-12-31

The United States Department of Energy (DOE) has generated and stored significant amounts of low-level mixed wastes consisting of radioactive materials mixed with hazardous chemical substances in various forms. The DOE is in the process of beginning a cleanup of these mixed wastes at many of its facilities. Many of these waste streams had been previously disposed of by methods acceptable at the time but with the passage of very stringent laws affecting migration of hazardous components, now the disposal areas constitute remediation sites. Disposal of low level radioactive waste potentially containing hazardous materials have also fallen under land disposal restrictions and currently no mixed waste is going to low level disposal facilities. The paper will address why the DOE is just now starting to comply with environmental laws, why there is a need to find more effective and less expensive means of cleaning up wastes, how the DOE is organizing to accomplish this cleanup, and several plasma technology development efforts in the DOE Complex that show promise of meeting these needs.

Volunteering as a pathway to productive and social engagement among older adults.

Science.gov (United States)

Morrow-Howell, Nancy; Lee, Yung Soo; McCrary, Stacey; McBride, Amanda

2014-10-01

Research on outcomes of volunteering in later life largely focuses on the health of volunteers. This is in contrast to studies of youth, where attention is directed toward the effects of volunteering on subsequent productive and citizen behaviors. In this study, we examined the effects of volunteering on subsequent social and civic activity of older adults. This study was conducted with volunteers from Experience Corps® (EC), a national program that brings older adults into schools to work with students. Data were derived from a baseline survey of older adults who were new EC volunteers in fall of 2006 and 2007. Follow-up interviews were conducted with 338 volunteers in fall 2010 to capture work, education, and community activities undertaken subsequent to joining EC. Subsequent to joining EC, 16% of volunteers reported that they started a new job, 53% started another volunteer position, 40% started a community activity, and 39% took a class/started educational program. When asked if and how EC participation played a role in their new involvements, 71% said it increased confidence, 76% said it increased realization of the importance of organized activities/daily structure, and more than 40% said they made social connections that led to new involvements. Most reported they were more likely to be involved in advocacy efforts for public education. Volunteering among older adults is a means as well as an end--just as it is for young people. Programs can do more to attract and serve older adults by promoting volunteering as a pathway to other engagements, including work, social, and civic activities. © 2014 Society for Public Health Education.

Effect of crystallochemistry of starting materials on the rate of smectite to illite reaction

International Nuclear Information System (INIS)

Sato, Tsutomu; Isobe, Hiroshi; Ohnuki, Toshihiko; Murakami, Takashi

1995-01-01

A series of hydrothermal experiments was performed to determine the effect of layer charge of starting materials on the smectite to illite reaction rate that might be applied to nuclear-waste repository design. The experiments were conducted on K-saturated fractions of Wyoming smectite (SWy-1) and Tsukinuno smectite (SKu-F) in a closed system at temperatures of 95, 150, 200, 250, 300 C for run durations of up to 477 days with a 1:20 mass ratio of solid to deionized water. The mean layer charge and tetrahedral charge of SKu-F are larger than those of SWy-1. The proportion of smectite layers in illite/smectite interstratified minerals rapidly decreases, and then slowly decreases with increase in reaction time; a plot of ln (100/% smectite) vs. time produces two distinct straight lines in all experiments. These lines are suggestive of two first-order kinetic processes with different rates for this reaction; the first process has a greater rate than the second one. An Arrhenius plot of the reaction rates for each process produces a folding and straight lines for the first and second processes, respectively, suggesting that there are at least two parallel processes in the first process, and a dominant process is different between high- and low-temperature reactions. The activation energies of the first and second processes determined from the plots are the same for the two starting materials, meaning that the reaction mechanisms for the two starting materials are the same. However, the rate of the first process is different between the two starting materials, although that of the second process is similar. The difference in the rate of the first process results possibly from the difference in the amount of layer charge between the two starting smectites

Assessment of the reliability and consistency of the "malnutrition inflammation score" (MIS) in Mexican adults with chronic kidney disease for diagnosis of protein-energy wasting syndrome (PEW).

Science.gov (United States)

González-Ortiz, Ailema Janeth; Arce-Santander, Celene Viridiana; Vega-Vega, Olynka; Correa-Rotter, Ricardo; Espinosa-Cuevas, María de Los Angeles

2014-10-04

The protein-energy wasting syndrome (PEW) is a condition of malnutrition, inflammation, anorexia and wasting of body reserves resulting from inflammatory and non-inflammatory conditions in patients with chronic kidney disease (CKD).One way of assessing PEW, extensively described in the literature, is using the Malnutrition Inflammation Score (MIS). To assess the reliability and consistency of MIS for diagnosis of PEW in Mexican adults with CKD on hemodialysis (HD). Study of diagnostic tests. A sample of 45 adults with CKD on HD were analyzed during the period June-July 2014.The instrument was applied on 2 occasions; the test-retest reliability was calculated using the Intraclass Correlation Coefficient (ICC); the internal consistency of the questionnaire was analyzed using Cronbach's αcoefficient. A weighted Kappa test was used to estimate the validity of the instrument; the result was subsequently compared with the Bilbrey nutritional index (BNI). The reliability of the questionnaires, evaluated in the patient sample, was ICC=0.829.The agreement between MIS observations was considered adequate, k= 0.585 (p <0.001); when comparing it with BNI, a value of k = 0.114 was obtained (p <0.001).In order to estimate the tendency, a correlation test was performed. The r² correlation coefficient was 0.488 (P <0.001). MIS has adequate reliability and validity for diagnosing PEW in the population with chronic kidney disease on HD. Copyright AULA MEDICA EDICIONES 2014. Published by AULA MEDICA. All rights reserved.

An Italian multicentre study on adult atopic dermatitis: persistent versus adult-onset disease.

Science.gov (United States)

Megna, Matteo; Patruno, Cataldo; Balato, Anna; Rongioletti, Franco; Stingeni, Luca; Balato, Nicola

2017-08-01

Atopic dermatitis (AD) is a chronic, recurrent, inflammatory skin disease which predominantly affects children. However, AD may persist until adulthood (persistent AD), or directly start in adults (adult-onset AD). AD often shows a non-flexural rash distribution, and atypical morphologic variants in adults and specific diagnostic criteria are lacking. Moreover, adult AD prevalence as well as detailed data which can characterize persistent vs adult-onset subtype are scant. The aim of this study was to investigate on the main features of adult AD particularly highlighting differences between persistent vs adult-onset form. An Italian multicentre observational study was conducted between April 2015-July 2016 through a study-specific digital database. 253 adult AD patients were enrolled. Familiar history of AD was negative in 81.0%. Erythemato-desquamative pattern was the most frequent clinical presentation (74.3%). Flexural surface of upper limbs was most commonly involved (47.8%), followed by eyelid/periocular area (37.9%), hands (37.2%), and neck (32%). Hypertension (7.1%) and thyroiditis (4.3%) were the most frequent comorbidities. A subgroup analysis between persistent (59.7%) vs adult-onset AD patients (40.3%) showed significant results only regarding AD severity (severe disease was more common in persistent group, p adult-onset disease), and comorbidities (hypertension was more frequent in adult-onset group, p Adult AD showed uncommon features such as significant association with negative AD family history and lacking of association with systemic comorbidities respect to general population. No significant differences among persistent vs adult-onset subgroup were registered except for hypertension, itch intensity, and disease severity.

30 CFR 75.1913 - Starting aids.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Starting aids. 75.1913 Section 75.1913 Mineral... SAFETY STANDARDS-UNDERGROUND COAL MINES Diesel-Powered Equipment § 75.1913 Starting aids. (a) Volatile fuel starting aids shall be used in accordance with recommendations provided by the starting aid...

A preliminary redrafting of the Italian technical guide no.26 on radioactive waste management

International Nuclear Information System (INIS)

Tocci, M.

1993-01-01

The recent National Energy Plan confirms the need for reprocessing of the nuclear spent fuel arising from the Nuclear Power Plants (NPPs) that were definitively put out of operation after Chernobyl accident. Two campaigns concerning the Italian spent fuel reprocessing are starting at this time. The first-one is related to LATINA (MAGNOX, GCR 160 MWe) while the second one will concern GARIGLIANO (BWR 160 MWe), CAORSO (BWR 840 MWe) and TRINO (PWR, 200 MWe). The first campaign will involve about 600 tons of MAGNOX spent fuel arising from LATINA NPP which will be reprocessed in the next future by BNFL (British Nuclear Fuel Limited) at Sellafield. The vitrified High Level Wastes (HLW) shall return to Italy starting from 1994. ENEA-DISP (Italian directorate for Nuclear Safety) has received from BNFL the technical specifications of the glass blocks. The approval of those specifications is scheduled by the end of 1993, in order to allow the delivery of the wastes. During the licensing iter ENEA-DISP will use its own Technical Guide N. 26, which identifies and specifies the basic criteria and requirements for an appropriate waste management policy. (author). 4 figs., 5 refs

Experience and projects concerning treatment, conditioning and storage of all radioactive wastes from Tokai reprocessing plant

International Nuclear Information System (INIS)

Fukuda, G.; Matsumoto, K.; Miyahara, K.

1984-01-01

The active operation of Tokai reprocessing plant started in September 1977, and about 170 t U of spent fuel were reprocessed between then and December 1982. During this period, the low-level waste processing plant reduced the amount of radioactivity discharged into the environment. For radioactive liquid waste, the treatment procedures consist mainly of evaporation to keep the discharge into the sea at a low level. For combustible low-level solid waste and the solvent waste, which is of low tributyl phosphate content, incineration has been used successfully (burned: about 150 t of combined LLSW, about 50 m 3 of solvent waste, i.e. diluent waste). Most of the past R and D work was devoted to reducing the activity discharged into the environment. Current R and D work is concerned with the treatment of solvent waste, the conditioning of solid wastes, the bituminization of low-level liquid waste and the vitrification of high-level liquid waste. The paper describes present practices, R and D work and future aspects of the treatment, conditioning and storage of all radioactive wastes from Tokai reprocessing plant. (author)

Press Start

Science.gov (United States)

Harteveld, Casper

This level sets the stage for the design philosophy called “Triadic Game Design” (TGD). This design philosophy can be summarized with the following sentence: it takes two to tango, but it takes three to design a meaningful game or a game with a purpose. Before the philosophy is further explained, this level will first delve into what is meant by a meaningful game or a game with a purpose. Many terms and definitions have seen the light and in this book I will specifically orient at digital games that aim to have an effect beyond the context of the game itself. Subsequently, a historical overview is given of the usage of games with a serious purpose which starts from the moment we human beings started to walk on our feet till our contemporary society. It turns out that we have been using games for all kinds of non-entertainment purposes for already quite a long time. With this introductory material in the back of our minds, I will explain the concept of TGD by means of a puzzle. After that, the protagonist of this book, the game Levee Patroller, is introduced. Based on the development of this game, the idea of TGD, which stresses to balance three different worlds, the worlds of Reality, Meaning, and Play, came into being. Interested? Then I suggest to quickly “press start!”

PROMETHEE: a versatile R and D measurement device for low level waste assay

International Nuclear Information System (INIS)

Romeyer Dherby, J.; Passard, C.; Mariani, A.

1996-01-01

The accurate measurement of heavy nuclide masses and activities in radioactive wastes drums is an important part of waste management. The Active/Passive non destructive assay of radioactive waste drums using a 14 MeV neutron generator is particularly interesting for alpha low level measurements or for gamma irradiating wastes. The development, optimisation, and validation of such a device for industrial use necessitate the building of a demonstrator. In 1985, the CEA decided to build at Cadarache the PROMETHEE modular system for experimenting the pulsed generator techniques, and since then, this device has led us to define several specific systems. At the present time, in the frame of COGEMA actions to reduce the volume of the reprocessing waste, a new strategy of drumming and incineration is going to start at LA HAGUE and MARCOULE, for the low level waste planned for surface storage. This strategy depends on the performance improvement of non destructive measurements systems used for the alpha waste evaluation. In this goal, a developments and tests are carried out on the PROMETHEE research and development facility at CEA CADARACHE, in order to obtain the required performances

PROMETHEE: a versatile R and D measurement device for low level waste assay

Energy Technology Data Exchange (ETDEWEB)

Romeyer Dherby, J.; Passard, C.; Mariani, A

1996-12-31

The accurate measurement of heavy nuclide masses and activities in radioactive wastes drums is an important part of waste management. The Active/Passive non destructive assay of radioactive waste drums using a 14 MeV neutron generator is particularly interesting for alpha low level measurements or for gamma irradiating wastes. The development, optimisation, and validation of such a device for industrial use necessitate the building of a demonstrator. In 1985, the CEA decided to build at Cadarache the PROMETHEE modular system for experimenting the pulsed generator techniques, and since then, this device has led us to define several specific systems. At the present time, in the frame of COGEMA actions to reduce the volume of the reprocessing waste, a new strategy of drumming and incineration is going to start at LA HAGUE and MARCOULE, for the low level waste planned for surface storage. This strategy depends on the performance improvement of non destructive measurements systems used for the alpha waste evaluation. In this goal, a developments and tests are carried out on the PROMETHEE research and development facility at CEA CADARACHE, in order to obtain the required performances.

Computationally based methodology for reengineering the high-level waste planning process at SRS

International Nuclear Information System (INIS)

Paul, P.K.; Gregory, M.V.; Wells, M.N.

1997-01-01

The Savannah River Site (SRS) has started processing its legacy of 34 million gallons of high-level radioactive waste into its final disposable form. The SRS high-level waste (HLW) complex consists of 51 waste storage tanks, 3 evaporators, 6 waste treatment operations, and 2 waste disposal facilities. It is estimated that processing wastes to clean up all tanks will take 30+ yr of operation. Integrating all the highly interactive facility operations through the entire life cycle in an optimal fashion-while meeting all the budgetary, regulatory, and operational constraints and priorities-is a complex and challenging planning task. The waste complex operating plan for the entire time span is periodically published as an SRS report. A computationally based integrated methodology has been developed that has streamlined the planning process while showing how to run the operations at economically and operationally optimal conditions. The integrated computational model replaced a host of disconnected spreadsheet calculations and the analysts' trial-and-error solutions using various scenario choices. This paper presents the important features of the integrated computational methodology and highlights the parameters that are core components of the planning process

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)

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)

Global burden of mortalities due to chronic exposure to ambient PM2.5 from open combustion of domestic waste

Science.gov (United States)

Kodros, John K.; Wiedinmyer, Christine; Ford, Bonne; Cucinotta, Rachel; Gan, Ryan; Magzamen, Sheryl; Pierce, Jeffrey R.

2016-12-01

Uncontrolled combustion of domestic waste has been observed in many countries, creating concerns for air quality; however, the health implications have not yet been quantified. We incorporate the Wiedinmyer et al (2014 Environ. Sci. Technol. 48 9523-30) emissions inventory into the global chemical-transport model, GEOS-Chem, and provide a first estimate of premature adult mortalities from chronic exposure to ambient PM2.5 from uncontrolled combustion of domestic waste. Using the concentration-response functions (CRFs) of Burnett et al (2014 Environ. Health Perspect. 122 397-403), we estimate that waste-combustion emissions result in 270 000 (5th-95th: 213 000-328 000) premature adult mortalities per year. The confidence interval results only from uncertainty in the CRFs and assumes equal toxicity of waste-combustion PM2.5 to all other PM2.5 sources. We acknowledge that this result is likely sensitive to choice of chemical-transport model, CRFs, and emission inventories. Our central estimate equates to 9% of adult mortalities from exposure to ambient PM2.5 reported in the Global Burden of Disease Study 2010. Exposure to PM2.5 from waste combustion increases the risk of premature mortality by more than 0.5% for greater than 50% of the population. We consider sensitivity simulations to uncertainty in waste-combustion emission mass, the removal of waste-combustion emissions, and model resolution. A factor-of-2 uncertainty in waste-combustion PM2.5 leads to central estimates ranging from 138 000 to 518 000 mortalities per year for factors-of-2 reductions and increases, respectively. Complete removal of waste combustion would only avoid 191 000 (5th-95th: 151 000-224 000) mortalities per year (smaller than the total contributed premature mortalities due to nonlinear CRFs). Decreasing model resolution from 2° × 2.5° to 4° × 5° results in 16% fewer mortalities attributed to waste-combustion PM2.5, and over Asia, decreasing resolution from 0.5° × 0.666° to 2° × 2

Implementation of 5S tools as a starting point in business process reengineering

Directory of Open Access Journals (Sweden)

Vorkapić Miloš 0000-0002-3463-8665

2017-01-01

Full Text Available The paper deals with the analysis of elements which represent a starting point in implementation of a business process reengineering. We have used Lean tools through the analysis of 5S model in our research. On the example of finalization of the finished transmitter in IHMT-CMT production, 5S tools were implemented with a focus on Quality elements although the theory shows that BPR and TQM are two opposite activities in an enterprise. We wanted to distinguish the significance of employees’ self-discipline which helps the process of product finalization to develop in time and without waste and losses. In addition, the employees keep their work place clean, tidy and functional.

Fly ash as a potential starting reagent for the synthesis of ultramarine blue

Energy Technology Data Exchange (ETDEWEB)

Landman, A.A.; De Waal, D. [University of Pretoria, Pretoria (South Africa). Dept. of Chemistry

2004-04-02

The traditional starting reagent for the synthesis of ultramarine blue, namely kaolin, has to be heated before the synthesis to weaken the structure of the kaolin. Two batches of fine fly ash (an aluminosilicate waste product from the combustion of coal) were successfully used to synthesize ultramarine blue. Infrared, Raman and X-ray diffraction results confirmed the formation of the product. Fly ash has the advantage over kaolin of being amorphous. The results further showed that the transition from the green ultramarine species to the blue species coincided with an increase in the ratio of the amount of S-3{sup -1} species relative to the amount of S-2{sup -1} species.

Prevention policies addressing packaging and packaging waste: Some emerging trends.

Science.gov (United States)

Tencati, Antonio; Pogutz, Stefano; Moda, Beatrice; Brambilla, Matteo; Cacia, Claudia

2016-10-01

Packaging waste is a major issue in several countries. Representing in industrialized countries around 30-35% of municipal solid waste yearly generated, this waste stream has steadily grown over the years even if, especially in Europe, specific recycling and recovery targets have been fixed. Therefore, an increasing attention starts to be devoted to prevention measures and interventions. Filling a gap in the current literature, this explorative paper is a first attempt to map the increasingly important phenomenon of prevention policies in the packaging sector. Through a theoretical sampling, 11 countries/states (7 in and 4 outside Europe) have been selected and analyzed by gathering and studying primary and secondary data. Results show evidence of three specific trends in packaging waste prevention policies: fostering the adoption of measures directed at improving packaging design and production through an extensive use of the life cycle assessment; raising the awareness of final consumers by increasing the accountability of firms; promoting collaborative efforts along the packaging supply chains. Copyright © 2016 Elsevier Ltd. All rights reserved.

Jump Starting Entrepreneurship

DEFF Research Database (Denmark)

Burcharth, Ana; Smith, Pernille; Frederiksen, Lars

How do laid-off employees become entrepreneurs after receiving a dream start into self-employment? This question is relevant for policy makers and entrepreneurship researchers alike since it raises the possibility of a reverse entrepreneurial opportunity, in which the chance of becoming an entrep......How do laid-off employees become entrepreneurs after receiving a dream start into self-employment? This question is relevant for policy makers and entrepreneurship researchers alike since it raises the possibility of a reverse entrepreneurial opportunity, in which the chance of becoming...... an entrepreneur emerges before the discovery of a profitable opportunity. We empirically examine this question on the unique setting of a corporate entrepreneurship program. In the midst of a corporate crisis, Nokia supported laid-off employees to start their own ventures under favorable conditions. We...... persevered in their endeavors and eventually became comfortable with their new career prospects. We discuss the psychological factors that impact career transition after organizational closure and theorize weather they encourage or discourage entrepreneurship....

Thermal treatment of historical radioactive solid and liquid waste into the CILVA incinerator

International Nuclear Information System (INIS)

Deckers, Jan; Mols, Ludo

2007-01-01

Since the very beginning of the nuclear activities in Belgium, the incineration of radioactive waste was chosen as a suitable technique for achieving an optimal volume reduction of the produced waste quantities. Based on the 35 years experience gained by the operation of the old incinerator, a new industrial incineration plant started nuclear operation in May 1995, as a part of the Belgian Centralized Treatment/Conditioning Facility named CILVA. Up to the end of 2006, the CILVA incinerator has burnt 1660 tonne of solid waste and 419 tonne of liquid waste. This paper describes the type and allowable radioactivity of the waste, the incineration process, heat recovery and the air pollution control devices. Special attention is given to the treatment of several hundreds of tonne historical waste from former reprocessing activities such as alpha suspected solid waste, aqueous and organic liquid waste and spent ion exchange resins. The capacity, volume reduction, chemical and radiological emissions are also evaluated. BELGOPROCESS, a company set up in 1984 at Dessel (Belgium) where a number of nuclear facilities were already installed is specialized in the processing of radioactive waste. It is a subsidiary of ONDRAF/NIRAS, the Belgian Nuclear Waste Management Agency. According to its mission statement, the activities of BELGOPROCESS focus on three areas: treatment, conditioning and interim storage of radioactive waste; decommissioning of shut-down nuclear facilities and cleaning of contaminated buildings and land; operating of storage sites for conditioned radioactive waste. (authors)

Gender Differences in Survival among Adult Patients Starting Antiretroviral Therapy in South Africa: A Multicentre Cohort Study

Science.gov (United States)

Cornell, Morna; Schomaker, Michael; Garone, Daniela Belen; Giddy, Janet; Hoffmann, Christopher J.; Lessells, Richard; Maskew, Mhairi; Prozesky, Hans; Wood, Robin; Johnson, Leigh F.; Egger, Matthias; Boulle, Andrew; Myer, Landon

2012-01-01

Background Increased mortality among men on antiretroviral therapy (ART) has been documented but remains poorly understood. We examined the magnitude of and risk factors for gender differences in mortality on ART. Methods and Findings Analyses included 46,201 ART-naïve adults starting ART between January 2002 and December 2009 in eight ART programmes across South Africa (SA). Patients were followed from initiation of ART to outcome or analysis closure. The primary outcome was mortality; secondary outcomes were loss to follow-up (LTF), virologic suppression, and CD4+ cell count responses. Survival analyses were used to examine the hazard of death on ART by gender. Sensitivity analyses were limited to patients who were virologically suppressed and patients whose CD4+ cell count reached >200 cells/µl. We compared gender differences in mortality among HIV+ patients on ART with mortality in an age-standardised HIV-negative population. Among 46,201 adults (65% female, median age 35 years), during 77,578 person-years of follow-up, men had lower median CD4+ cell counts than women (85 versus 110 cells/µl, p<0.001), were more likely to be classified WHO stage III/IV (86 versus 77%, p<0.001), and had higher mortality in crude (8.5 versus 5.7 deaths/100 person-years, p<0.001) and adjusted analyses (adjusted hazard ratio [AHR] 1.31, 95% CI 1.22–1.41). After 36 months on ART, men were more likely than women to be truly LTF (AHR 1.20, 95% CI 1.12–1.28) but not to die after LTF (AHR 1.04, 95% CI 0.86–1.25). Findings were consistent across all eight programmes. Virologic suppression was similar by gender; women had slightly better immunologic responses than men. Notably, the observed gender differences in mortality on ART were smaller than gender differences in age-standardised death rates in the HIV-negative South African population. Over time, non-HIV mortality appeared to account for an increasing proportion of observed mortality. The analysis was limited by missing

Gender differences in survival among adult patients starting antiretroviral therapy in South Africa: a multicentre cohort study.

Directory of Open Access Journals (Sweden)

Morna Cornell

Full Text Available Increased mortality among men on antiretroviral therapy (ART has been documented but remains poorly understood. We examined the magnitude of and risk factors for gender differences in mortality on ART.Analyses included 46,201 ART-naïve adults starting ART between January 2002 and December 2009 in eight ART programmes across South Africa (SA. Patients were followed from initiation of ART to outcome or analysis closure. The primary outcome was mortality; secondary outcomes were loss to follow-up (LTF, virologic suppression, and CD4+ cell count responses. Survival analyses were used to examine the hazard of death on ART by gender. Sensitivity analyses were limited to patients who were virologically suppressed and patients whose CD4+ cell count reached >200 cells/µl. We compared gender differences in mortality among HIV+ patients on ART with mortality in an age-standardised HIV-negative population. Among 46,201 adults (65% female, median age 35 years, during 77,578 person-years of follow-up, men had lower median CD4+ cell counts than women (85 versus 110 cells/µl, p<0.001, were more likely to be classified WHO stage III/IV (86 versus 77%, p<0.001, and had higher mortality in crude (8.5 versus 5.7 deaths/100 person-years, p<0.001 and adjusted analyses (adjusted hazard ratio [AHR] 1.31, 95% CI 1.22-1.41. After 36 months on ART, men were more likely than women to be truly LTF (AHR 1.20, 95% CI 1.12-1.28 but not to die after LTF (AHR 1.04, 95% CI 0.86-1.25. Findings were consistent across all eight programmes. Virologic suppression was similar by gender; women had slightly better immunologic responses than men. Notably, the observed gender differences in mortality on ART were smaller than gender differences in age-standardised death rates in the HIV-negative South African population. Over time, non-HIV mortality appeared to account for an increasing proportion of observed mortality. The analysis was limited by missing data on baseline HIV disease

Status of radioactive waste management in Taiwan

International Nuclear Information System (INIS)

Huang, C.C.

1993-01-01

Taiwan started to generate nuclear power in 1977. The peaceful uses of nuclear energy generated radwaste. The major radwaste generators are nuclear power plants of Taiwan Power Company (Taipower). The other generators are the Institute of Nuclear Energy Research (INER), industry, medicine, agriculture, and education. Radwaste Administration (RWA), a subsidiary of Atomic Energy Council (AEC), is the regulatory body of radwaste in Taiwan. Radwaste management projects in Taiwan include: (1) construction of a Volume Reduction Center (VRC); (2) construction of a low-level radwaste transport ship; (3) construction of low-level waste final disposal facility; (4) construction of a spent fuel interim storage facility; (5) construction of spent fuel disposal facility. In the near future, final disposal of low-level waste is the most important work of both Taipower and RWA. Both organizations will put much more effort into this work

Treatment of low alpha activity liquid wastes

International Nuclear Information System (INIS)

Nannicini, R.; Fenoglio, F.; Pozzi, L.

1984-01-01

The nuclear industry considers so big safety problems that the purifying treatment of liquid wastes must always provide for a complete recycle of the liquid strems from the production processes as regard this problem. ''Enea-Comb-Ifec'' people from saluggia, already previously engages with verifying and setting-up ''Sol-Gel'' process for the recover of uranium-plutonium solutions coming from irradiated fuel reprocessing, started an experimental work, with the assistance of ''Cnr-Irsa'' from Rome, on the applicability of the biological treatment to the purification of liquid wastes coming from the production process itself. The present technical report gives, besides a short description of the ''Sol-Gel'' process, the first results, only relating to the biological stage of the whole proposed purifyng treatment, included the final results of the experimental work, object of a contract between ''Enea-Ifec'' and ''Snam progetti'' from Fano

High-level waste borosilicate glass a compendium of corrosion characteristics. Volume 1

International Nuclear Information System (INIS)

Cunnane, J.C.

1994-03-01

Current plans call for the United States Department of Energy (DOE) to start up facilities for vitrification of high-level radioactive waste (HLW) stored in tanks at the Savannah River Site, Aiken, South Carolina, in 1995; West Valley Demonstration Project, West Valley, New York, in 1996; and at the Hanford Site, Richland, Washington, after the year 2000. The product from these facilities will be canistered HLW borosilicate glass, which will be stored, transported, and eventually disposed of in a geologic repository. The behavior of this glass waste product, under the range of likely service conditions, is the subject of considerable scientific and public interest. Over the past few decades, a large body of scientific information on borosilicate waste glass has been generated worldwide. The intent of this document is to consolidate information pertaining to our current understanding of waste glass corrosion behavior and radionuclide release. The objective, scope, and organization of the document are discussed in Section 1.1, and an overview of borosilicate glass corrosion is provided in Section 1.2. The history of glass as a waste form and the international experience with waste glass are summarized in Sections 1.3 and 1.4, respectively

The mythology of waste disposal

International Nuclear Information System (INIS)

Beckhofer.

1981-10-01

This paper, while making a parallel between the mythology of the dangers of alcohol when the United States adopted a constitutional amendment prohibiting intoxicating liquor and public attitudes towards the dangers of nuclear waste burial, outlines the reason for these attitudes. Poor information of the public, from the start, on such dangers, the trauma of the atomic bomb and certain court decisions on nuclear activities which were in fact repealed by the Supreme Court. The paper also stresses the difficulty of dealing with this problem on a rational basis despite proven technical knowledge and successful experiments. (NEA) [fr

THE MURMANSK INITIATIVE - RF: COMPLETING CONSTRUCTION AND START-UP TESTING

International Nuclear Information System (INIS)

CZAJKOWSKI, C.; BOWERMAN, B.S.; DYER, R.S.; SORLIE, A.A.; WESTER, D.

1998-01-01

The Murmansk Initiative - RF was instigated to address Russia's ability to meet the London Convention prohibiting ocean dumping of radioactive waste. The Initiative, under a trilateral agreement, will upgrade an existing low-level liquid radioactive waste treatment facility, increasing capacity from 1,200 m 3 /year to 5,000 m 3 /year, and expand the capability to treat liquids containing salt (up to 10 g/L). The three parties to the agreement, the Russian Federation, Norway, and the US, have split the costs for the project. All construction has been provided by Russia. Construction of mechanical systems (piping and valves, pumps, sorbent columns, settling tanks, surge tanks) is nearly complete, with instrumentation and control (I+C) systems the last to be installed. Delays to the I+C installation have occurred because changes in system specifications required some additional US-supplied computer control equipment to be purchased, and clearance through customs (both US and Russian) has been slow. Start-up testing has been limited to testing of some isolated sub-systems because of the delays in I+C installation. Final construction activities are also hampered by the current state of the Russian economy. The specific impact has been completion of the cementation unit, which was not funded under the trilateral agreement (but funded by the Russian government). Russian regulatory authorities have stated that final licensing for expanded capacity (5,000 m 3 /year) will not be given until the cementation unit is on-line

Success in siting low-level radioactive waste management facilities

International Nuclear Information System (INIS)

Brown, P.; McCauley, D.

2001-01-01

Full text: The Government of Canada is about to conclude a legal agreement with three municipalities that will result in a $260-million 10-year multi-phase project to cleanup low-level radioactive wastes and contaminated soils and establish long-term low-level radioactive waste management facilities. Over the last two decades, numerous efforts were undertaken to resolve this long-standing environmental issue. Finally, the communities where the wastes are located came forward with resolutions that they were willing to develop local solutions to the problem. All three municipalities, facilitated by Government funding and assistance, put forward their own local solution to their own waste problem. Government accepted the municipalities' proposals as the basis of a comprehensive approach for dealing with the local problem. Negotiations ensued on Principles of Understanding under which the cleanup would proceed and new long-term waste management facilities would be established. Government's acceptance of the negotiated Principles led to the preparation of a legal agreement that was subsequently signed by each of the municipalities and is now about to be ratified by the Government of Canada. Resolution of the issue will be a major milestone in the Government's environmental agenda. The project will result in an environmentally-responsible, safe, and publicly-accepted approach to the long-term management of the wastes and remove one of the largest contaminated sites issues from the Government's agenda. It also advances the Government's nuclear waste policy and indicates to waste producers that the Government is developing and implementing solutions for wastes for which it is responsible. A key lesson for the Government of Canada in this process has been the advantages of a locally-generated solution. Through the process, the Government empowered the local municipalities to develop their own solution to the local waste problem. It facilitated and supported that effort

Time for action. Disposal of radioactive wastes is a task regarding all of us; Zeit zum Handeln. Die Entsorgung radioaktiver Abfaelle geht uns alle an

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-11-15

This report helps to the popularization of the Nagra works accomplished for the management and disposal of the radioactive wastes in Switzerland. In Switzerland the disposal of radioactive wastes is clearly regulated. The disposal programme describes the process according to which the long-term storage of radioactive wastes has to be implemented to guaranty safety for mankind and environment. The disposal of radioactive wastes in deep geological repositories is a task of national importance. Until a deep repository can get into operation, several licence stages are necessary. After the overall licence given by the Federal Council is accepted by the parliament, it may still be the subject of an optional referendum. There are three different types of radioactive wastes: the low- and intermediate-level wastes (L/ILW) and the high-level wastes (HLW). Two different deep geological repositories are needed, one for the L/ILW wastes and another one for the HLW wastes. Before the repositories begin operation, the wastes are stored on the ground in interim storage facilities. The general licence for the construction of the repositories is expected to be granted before 2020. Afterwards the construction of both repositories can be undertaken. The repository for L/ILW wastes will not start operation before 2030. The start of operation of the repository for HLW wastes is not expected before 2040. This repository will be designed in such a way that the spent fuel assemblies which are stored as HLW wastes, could be withdrawn even after the closure of the repository.

Waste reduction program at Oak Ridge National Laboratory during CY 1990

International Nuclear Information System (INIS)

Homan, M.D.; Kendrick, C.M.; Schultz, R.M.

1991-03-01

Oak Ridge National Laboratory is a multipurpose research and development facility owned and operated by the Department of Energy and managed under subcontract by Martin Marietta Energy Systems, Inc. ORNL's primary role is the support of energy technology through applied research and engineering development and scientific research in basic and physical sciences. ORNL also is a valuable resource in the quest to solve problems of national importance, such as nuclear and chemical waste management. In addition, ORNL produces useful radioactive and stable isotopes for medical and energy research that are unavailable from the private sector. These activities are conducted predominantly on small scales in over 900 individual R ampersand D laboratories at ORNL. Activities are diverse, variable, and frequently generate some type of waste material. In contrast to the typical production facility's few large-volume waste ''streams,'' ORNL has numerous small ones, including radioactive LLLW, liquid PW, solid radioactive waste (LLW and TRU waste), hazardous waste, industrial waste, and mixed waste (containing both hazardous and radioactive constituents). The wide diversity of waste complicates both management and compliance with reporting requirements that are designed to apply to production facilities. The reduction of all ORNL waste generation is an economically logical response to the rising costs and liabilities of waste management and disposal. Human health and the environment are best protected from all types of wastes by prevention of their generation from the start. At ORNL, efforts to minimize many wastes have been mandated by federal regulations and DOE, Energy Systems, and internal policies. Real progress has been achieved. As researchers become increasingly aware of the advantages of improving the efficiency of their procedures and as divisions launch systematic evaluations of activities with reduction potential, further reductions will be achieved. 24 refs., 8 figs

Greenhouse gases emission from municipal waste management: The role of separate collection.

Science.gov (United States)

Calabrò, Paolo S

2009-07-01

The municipal solid waste management significantly contributes to the emission in the atmosphere of greenhouse gases (e.g. CO(2), CH(4), N(2)O) and therefore the management process from collection to treatment and disposal has to be optimized in order to reduce these emissions. In this paper, starting from the average composition of undifferentiated municipal solid waste in Italy, the effect of separate collection on greenhouse gases emissions from municipal waste management has been assessed. Different combinations of separate collection scenarios and disposal options (i.e. landfilling and incineration) have been considered. The effect of energy recovery from waste both in landfills and incinerators has also been addressed. The results outline how a separate collection approach can have a significant effect on the emission of greenhouse gases and how wise municipal solid waste management, implying the adoption of Best Available Technologies (i.e. biogas recovery and exploitation system in landfills and energy recovery system in Waste to Energy plants), can not only significantly reduce greenhouse gases emissions but, in certain cases, can also make the overall process a carbon sink. Moreover it has been shown that separate collection of plastic is a major issue when dealing with global warming relevant emissions from municipal solid waste management.

Entry correlates and motivations of older adults participating in organized exercise programs

NARCIS (Netherlands)

Stiggelbout, M.; Hopman-Rock, M.; Mechelen, W. van

2008-01-01

This study reports entry correlates and motivations of older adults participating in organized exercise programs in the Netherlands, as determined in a descriptive explorative study (N = 2,350, response rate 86%). Participants were community-dwelling older adults (50+ years) who enrolled and started

Decision basis for a Danish ultimate storage for low and intermediate radioactive wastes

International Nuclear Information System (INIS)

2008-11-01

In 2003 the Danish Parliament consented to let the government start the preparation of a basis for decision on a Danish ultimate storage for low and intermediate radioactive wastes. The present report was prepared by a working group and it presents the final proposal for such a decision basis. The report describes the fundamental safety and environmental principles for establishing an ultimate storage, including determining the principles for site selection, storage construction, and safety analysis. In an appendix, the amount, types, and activity level of the Danish radioactive wastes are presented. (ln)

Champion for radioactive waste disposal host of the WIPP: Carlsbad, New Mexico

International Nuclear Information System (INIS)

Rempe, N.T.

1995-01-01

The city of Carlsbad, New Mexico, volunteered to host the United States' first final repository for radioactive waste. Carlsbad citizens and their leaders understood that after decades of accumulating waste, the time had come to close the nuclear cycle. They therefore agreed to support the Waste Isolation Pilot Plant (WIPP), provided the project would not endanger its neighbors or the environment. The southeastern New Mexico area offers several advantages for deep geologic waste disposal: The regional geology is well understood. Massive salt beds are an excellent repository medium. Decades of potash mining experience inspired confidence in that concept. In underground nuclear test in the salt had caused no harm. And the city was seeking opportunities to diversify its economic base. Through the growth of the project, beginning in 1971, Carlsbad has demonstrated unwavering commitment, patience, and persistence. Without these attitudes, the WIPP would certainly not be where it is today and most likely would not exist at all. Civic leaders made the critical difference as the project weathered repeated challenges. With the support of their constituents, they foiled anti-nuclear obstructionism and advanced the project at every turn, frequently on their own time and at their own expense. The WIPP is now scheduled to start disposal in 1998, after a ten-year delay from its originally intended opening date. If it still has a realistic chance to start operations before the end of the century, the credit must in no small measure go to the city and the citizens of Carlsbad, New Mexico

The Welding Effect on Mechanical Strength of Low Level Radioactive Waste Drum Container

International Nuclear Information System (INIS)

Aisyah; Herlan Martono

2007-01-01

The treatment of compactable low level solid waste was started by compaction of 100 liter drum containing the waste using 600 kN hydraulic press in 200 liters drum. The 200 liter drum of waste container containing of compacted waste then immobilized with cement and stored in interm storage. The 200 liter drum of waste container made of carbon steel material to comply with a good mechanical strength request in order to be able to retain the waste content for long period. Welding is a one step in a waste drum container fabrication process that has an opportunity in decreasing these mechanical strength. The research is carried out by welding the waste drum container material sample by electric arc welding. Mechanical strength test carried out by measuring the tensile strength by using the tensile strength machine, hardness test by using Vickers hardness test and microstructure observation by using the optic microscope. The result shows that the welding cause the microstructure changes, its meaning of forming ferro oxide phase on welding area that leads to the brittle material, so that the mechanical strength has a decreasing slightly. Nevertheless the decreasing of mechanical strength is still in the range of safety limit. (author)

76 FR 50813 - Major Capital Investment Projects; Guidance on News Starts/Small Starts Policies and Procedures

Science.gov (United States)

2011-08-16

... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Major Capital Investment Projects; Guidance on News Starts/Small Starts Policies and Procedures AGENCY: Federal Transit Administration (FTA... Administration (FTA) to publish policy guidance on the New and Small Starts capital project review and evaluation...

Technique for Reduction of Environmental Pollution from Construction Wastes

Science.gov (United States)

Bakaeva, N. V.; Klimenko, M. Y.

2017-11-01

The results of the research on the negative impact construction wastes have on the urban environment and construction ecological safety are described. The research results are based on the statistical data and indicators calculated with the use of environmental pollution assessment in the restoration system of urban buildings technical conditions. The technique for the reduction of environmental pollution from construction wastes is scientifically based on the analytic summary of scientific and practical results for ecological safety ensuring at major overhaul and current repairs (reconstruction) of the buildings and structures. It is also based on the practical application of the probability theory method, system analysis and disperse system theory. It is necessary to execute some stages implementing the developed technique to reduce environmental pollution from construction wastes. The stages include various steps starting from information collection to the system formation with optimum performance characteristics which are more resource saving and energy efficient for the accumulation of construction wastes from urban construction units. The following tasks are solved under certain studies: basic data collection about construction wastes accumulation; definition and comparison of technological combinations at each system functional stage intended for the reduction of construction wastes discharge into the environment; assessment criteria calculation of resource saving and energy efficiency; optimum working parameters of each implementation stage are created. The urban construction technique implementation shows that the resource saving criteria are from 55.22% to 88.84%; potential of construction wastes recycling is 450 million tons of construction damaged elements (parts).

Study on retrievability of waste package in geological disposal

International Nuclear Information System (INIS)

Hasegawa, Hiroshi; Noda, Masaru

2002-02-01

Retrievability of waste packages in geological disposal of high-level radioactive waste has been investigated from a technical aspect in various foreign countries, reflecting a social concern while retrievability is not provided as a technical requirement. This study investigates the concept of reversibility and retrievability in foreign countries and a technical feasibility on retrievability of waste packages in the geological disposal concept shown in the H12 report. The conclusion obtained through this study is as follows: 1. Concept of reversibility and retrievability in foreign countries. Many organizations have reconsidered the retrievability as one option in the geological disposal to improve the reversibility of the stepwise decision-making process and provide the flexibility, even based upon the principle of the geological disposal that retrieval of waste from the repository is not intended. 2. Technical feasibility on the retrievability in disposal concept in the H12 report. It is confirmed to be able to remove the buffer and to retrieve the waste packages by currently available technologies even after the stages following emplacement of the buffer. It must be noted that a large effort and expense would be required for some activities such as the reconstruction of access route if the activities started after a stage of backfilling disposal tunnels. 3. Evaluation of feasibility on the retrievability and extraction of the issues. In the near future, it is necessary to study and confirm the practical workability and economical efficiency for the retrieving method of waste packages proposed in this study, the handling and processing method of removed buffer materials, and the retrieving method of waste packages in the case of degrading the integrity of waste packages or not emplacing the waste packages in the assumed attitude, etc. (author)

State and Federal activities on low-level waste

International Nuclear Information System (INIS)

1983-01-01

With the passage of the Low-Level Waste Policy Act in December 1980, the states have assumed the management responsibility and the federal government has become a facilitator. State and Federal roles in regulation have not altered. This paper reviews the developments over the last two years to point out the progress made and critical steps that lie ahead. Both technological and political aspects are covered, and a conclusion is presented with a look to the future. Since compact development in the tool chosen by the politicans for low-level waste management, the author reviews the present status starting with the northwest compact which has been introduced into the House and Senate and is subject to hearings. The past two years have seen real progress in technology in the broadest sense. An information development and dissemination system was established in 1978 wih the state-by-state assessment of low-level waste disposal. Annual examinations have been made through 1981 which enables one to understand the generation of low-level wastes. Policy level planning by states can be supported by the base level of information available. Incineration of dry active waste and other non-fuel cycle waste is ready to be fully accepted. Much work has been done on volume reduction of liquids. The increased understanding of the ways to make a disposal site work represents a major technolological improvement. Within the DOE system, there is beginning to be a real understanding of the critical parameters in disposal site performance in the East

Waste Sites - Municipal Waste Operations

Data.gov (United States)

NSGIC Education | GIS Inventory — A Municipal Waste Operation is a DEP primary facility type related to the Waste Management Municipal Waste Program. The sub-facility types related to Municipal Waste...

Drug waste minimisation and cost-containment in Medical Oncology: Two-year results of a feasibility study

Directory of Open Access Journals (Sweden)

Mansutti Mauro

2008-04-01

Full Text Available Abstract Background Cost-containment strategies are required to face the challenge of rising drug expenditures in Oncology. Drug wastage leads to economic loss, but little is known about the size of the problem in this field. Methods Starting January 2005 we introduced a day-to-day monitoring of drug wastage and an accurate assessment of its costs. An internal protocol for waste minimisation was developed, consisting of four corrective measures: 1. A rational, per pathology distribution of chemotherapy sessions over the week. 2. The use of multi-dose vials. 3. A reasonable rounding of drug dosages. 4. The selection of the most convenient vial size, depending on drug unit pricing. Results Baseline analysis focused on 29 drugs over one year. Considering their unit price and waste amount, a major impact on expense was found to be attributable to six drugs: cetuximab, docetaxel, gemcitabine, oxaliplatin, pemetrexed and trastuzumab. The economic loss due to their waste equaled 4.8% of the annual drug expenditure. After the study protocol was started, the expense due to unused drugs showed a meaningful 45% reduction throughout 2006. Conclusion Our experience confirms the economic relevance of waste minimisation and may represent a feasible model in addressing this issue. A centralised unit of drug processing, the availability of a computerised physician order entry system and an active involvement of the staff play a key role in allowing waste reduction and a consequent, substantial cost-saving.

Glass optimization for vitrification of Hanford Site low-level tank waste

International Nuclear Information System (INIS)

Feng, X.; Hrma, P.R.; Westsik, J.H. Jr.

1996-03-01

The radioactive defense wastes stored in 177 underground single-shell tanks (SST) and double-shell tanks (DST) at the Hanford Site will be separated into low-level and high-level fractions. One technology activity underway at PNNL is the development of glass formulations for the immobilization of the low-level tank wastes. A glass formulation strategy has been developed that describes development approaches to optimize glass compositions prior to the projected LLW vitrification facility start-up in 2005. Implementation of this strategy requires testing of glass formulations spanning a number of waste loadings, compositions, and additives over the range of expected waste compositions. The resulting glasses will then be characterized and compared to processing and performance specifications yet to be developed. This report documents the glass formulation work conducted at PNL in fiscal years 1994 and 1995 including glass formulation optimization, minor component impacts evaluation, Phase 1 and Phase 2 melter vendor glass development, liquidus temperature and crystallization kinetics determination. This report also summarizes relevant work at PNNL on high-iron glasses for Hanford tank wastes conducted through the Mixed Waste Integrated Program and work at Savannah River Technology Center to optimize glass formulations using a Plackett-Burnam experimental design

45 CFR 1308.21 - Parent participation and transition of children into Head Start and from Head Start to public...

Science.gov (United States)

2010-10-01

... into Head Start and from Head Start to public school. 1308.21 Section 1308.21 Public Welfare... AND HUMAN SERVICES THE ADMINISTRATION FOR CHILDREN, YOUTH AND FAMILIES, HEAD START PROGRAM HEAD START... Standards § 1308.21 Parent participation and transition of children into Head Start and from Head Start to...

A Call for Methodological Plurality: Reconsidering Research Approaches in Adult Education

Science.gov (United States)

Daley, Barbara J.; Martin, Larry G.; Roessger, Kevin M.

2018-01-01

Within this "Adult Education Quarterly" ("AEQ") forum, the authors call for a dialogue and examination of research methods in the field of adult and continuing education. Using the article by Boeren as a starting point, the authors analyze both qualitative and quantitative research trends and advocate for more methodological…

Tank waste remediation system integrated technology plan. Revision 2

International Nuclear Information System (INIS)

Eaton, B.; Ignatov, A.; Johnson, S.; Mann, M.; Morasch, L.; Ortiz, S.; Novak, P.

1995-01-01

The Hanford Site, located in southeastern Washington State, is operated by the US Department of Energy (DOE) and its contractors. Starting in 1943, Hanford supported fabrication of reactor fuel elements, operation of production reactors, processing of irradiated fuel to separate and extract plutonium and uranium, and preparation of plutonium metal. Processes used to recover plutonium and uranium from irradiated fuel and to recover radionuclides from tank waste, plus miscellaneous sources resulted in the legacy of approximately 227,000 m 3 (60 million gallons) of high-level radioactive waste, currently in storage. This waste is currently stored in 177 large underground storage tanks, 28 of which have two steel walls and are called double-shell tanks (DSTs) an 149 of which are called single-shell tanks (SSTs). Much of the high-heat-emitting nuclides (strontium-90 and cesium-137) has been extracted from the tank waste, converted to solid, and placed in capsules, most of which are stored onsite in water-filled basins. DOE established the Tank Waste Remediation System (TWRS) program in 1991. The TWRS program mission is to store, treat, immobilize and dispose, or prepare for disposal, the Hanford tank waste in an environmentally sound, safe, and cost-effective manner. Technology will need to be developed or improved to meet the TWRS program mission. The Integrated Technology Plan (ITP) is the high-level consensus plan that documents all TWRS technology activities for the life of the program

Tank waste remediation system integrated technology plan. Revision 2

Energy Technology Data Exchange (ETDEWEB)

Eaton, B.; Ignatov, A.; Johnson, S.; Mann, M.; Morasch, L.; Ortiz, S.; Novak, P. [eds.] [Pacific Northwest Lab., Richland, WA (United States)

1995-02-28

The Hanford Site, located in southeastern Washington State, is operated by the US Department of Energy (DOE) and its contractors. Starting in 1943, Hanford supported fabrication of reactor fuel elements, operation of production reactors, processing of irradiated fuel to separate and extract plutonium and uranium, and preparation of plutonium metal. Processes used to recover plutonium and uranium from irradiated fuel and to recover radionuclides from tank waste, plus miscellaneous sources resulted in the legacy of approximately 227,000 m{sup 3} (60 million gallons) of high-level radioactive waste, currently in storage. This waste is currently stored in 177 large underground storage tanks, 28 of which have two steel walls and are called double-shell tanks (DSTs) an 149 of which are called single-shell tanks (SSTs). Much of the high-heat-emitting nuclides (strontium-90 and cesium-137) has been extracted from the tank waste, converted to solid, and placed in capsules, most of which are stored onsite in water-filled basins. DOE established the Tank Waste Remediation System (TWRS) program in 1991. The TWRS program mission is to store, treat, immobilize and dispose, or prepare for disposal, the Hanford tank waste in an environmentally sound, safe, and cost-effective manner. Technology will need to be developed or improved to meet the TWRS program mission. The Integrated Technology Plan (ITP) is the high-level consensus plan that documents all TWRS technology activities for the life of the program.

Swedish Nuclear Waste Management from Theory to Practice

International Nuclear Information System (INIS)

Holmqvist, Magnus

2008-01-01

The programme has evolved from a project of a few experts drawing up the outline of what today is a comprehensive programme of research, development, demonstration, design, construction and operation of facilities for radioactive waste management. The Swedish programme was greatly influenced at an early stage by political actions, which included placing the responsibility with the reactor owners to demonstrate safe disposal of spent nuclear fuel and also to fund a disposal programme. The response of the reactor owners was to immediately start the KBS project. Its third report in 1983 described the KBS-3 concept, which is still the basis for SKB's deep geological repository system. Thus, this year is the 25th anniversary of the creation of the well-known KBS-3 concept. The SKB programme for nuclear waste management is today divided in two sub programmes; LILW Programme and the Nuclear Fuel Programme. The LILW Programme is entering into a new phase with the imminent site investigations for the expansion of the SFR LILW repository, which is in operation since 1988, to accept also decommissioning waste. The expansion of SFR is driven by a government decision urging SKB to investigate when a licensing of a repository for decommissioning waste can be made

Anaerobic digestion and co-digestion of slaughterhouse wastes

Directory of Open Access Journals (Sweden)

Sonia Castellucci

2013-09-01

Full Text Available The use of renewable energy is becoming increasingly necessary in order to address the global warming problem and, as a consequence, has become an high priority for many countries. Biomass is a clean and renewable energy source with growing potential to replace conventional fossil fuels. Among biomass, residual and waste ones represent a great resource for energy generation since they permit both to eliminate a possible waste and to produce energy. In the present work, the case of slaughterhouse wastes (SHWs has been investigated. Anaerobic digestion is nowadays considered as one of the most important and sustainable conversion technology exploiting organic matter and biodegradable wastes. Biogas results from this bio-chemical process and mainly consists of methane and carbon dioxide, leading to produce thermal energy and/or electricity. In this paper, the European Regulations on animal by-products (ABPs are described, and some previous study on anaerobic digestion and co-digestion of ABPs - more precisely SHWs - are considered and compared in order to fix a starting point for future tests on their co-digestion in a micro-scale pilot digester. This is to define optimal feed ratio values which ensure an increasing content of methane in the outgoing biogas.

The Advantages of Fixed Facilities in Characterizing TRU Wastes

International Nuclear Information System (INIS)

FRENCH, M.S.

2000-01-01

In May 1998 the Hanford Site started developing a program for characterization of transuranic (TRU) waste for shipment to the Waste Isolation Pilot Plant (WIPP) in New Mexico. After less than two years, Hanford will have a program certified by the Carlsbad Area Office (CAO). By picking a simple waste stream, taking advantage of lessons learned at the other sites, as well as communicating effectively with the CAO, Hanford was able to achieve certification in record time. This effort was further simplified by having a centralized program centered on the Waste Receiving and Processing (WRAP) Facility that contains most of the equipment required to characterize TRU waste. The use of fixed facilities for the characterization of TRU waste at sites with a long-term clean-up mission can be cost effective for several reasons. These include the ability to control the environment in which sensitive instrumentation is required to operate and ensuring that calibrations and maintenance activities are scheduled and performed as an operating routine. Other factors contributing to cost effectiveness include providing approved procedures and facilities for handling hazardous materials and anticipated contingencies and performing essential evolutions, and regulating and smoothing the work load and environmental conditions to provide maximal efficiency and productivity. Another advantage is the ability to efficiently provide characterization services to other sites in the Department of Energy (DOE) Complex that do not have the same capabilities. The Waste Receiving and Processing (WRAP) Facility is a state-of-the-art facility designed to consolidate the operations necessary to inspect, process and ship waste to facilitate verification of contents for certification to established waste acceptance criteria. The WRAP facility inspects, characterizes, treats, and certifies transuranic (TRU), low-level and mixed waste at the Hanford Site in Washington state. Fluor Hanford operates the $89

Disposal of low-level radioactive waste at the Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Sauls, V.W. [Dept. of Energy, Aiken, SC (United States). Savannah River Field Office

1993-03-01

An important objective of the Savannah River Site`s low-level radioactive waste management program is to isolate the waste from the environment both now and well into the future. A key element in achieving this is the disposal of low-level radioactive waste in sealed concrete vaults. Historically the Site has disposed of low-level radioactive waste via shallow land burial. In 1987, it was decided that better isolation from the environment was required. At that time several options for achieving this isolation were studied and below grade concrete vaults were chosen as the best method. This paper discusses the performance objectives for the vaults, the current design of the vaults and plans for the design of future vaults, the cost to construct the vaults, and the performance assessment on the vaults. Construction of the first set of vaults is essentially complete and readiness reviews before the start of waste receipt are being performed. Startup is to begin late in calendar year 1992 and continue through early CY 1993. The performance assessment is under way and the first draft is to be completed in early 1993.