Wood versus plant fibers: Similarities and differences in composite applications

DEFF Research Database (Denmark)

Madsen, Bo; Gamstedt, E. Kristofer

2013-01-01

-negligible porosity content, and finally, the moisture sensitivity of the composites. The performance of wood and plant fiber composites is compared to the synthetic glass and carbon fibers conventionally used for composites, and advantages and disadvantages of the different fibers are discussed. © 2013 Bo Madsen......The work on cellulose fiber composites is typically strictly divided into two separated research fields depending on the fiber origin, that is, from wood and from annual plants, representing the two different industries of forest and agriculture, respectively. The present paper evaluates...... in parallel wood fibers and plant fibers to highlight their similarities and differences regarding their use as reinforcement in composites and to enable mutual transfer of knowledge and technology between the two research fields. The paper gives an introduction to the morphology, chemistry...

FTIR fiber optic methods for the analysis of Hanford Site waste

International Nuclear Information System (INIS)

Rebagay, T.V.; Cash, R.J.; Dodd, D.A.

1995-06-01

Sampling and chemical characterization of mixed high-level waste stored in underground tanks at the Hanford Site is currently in progress. Waste tank safety concerns have provided impetus to analyze this waste. A major safety issue is the possibility of significant concentrations of fuel (ferrocyanide and/or organic compounds) in contact with oxidizers (nitrates and nitrites). It is postulated that under dry conditions and elevated temperatures, ferrocyanide- and/or organic-bearing wastes could undergo rapid exothermic reactions. To maintain the tanks in a safe condition, data are needed on the moisture and fuel concentrations in the waste. Because of the highly radioactive nature of the waste, non-radioactive waste simulants mimicking actual waste are used to provide an initial basis for identifying realistic waste tank safety concerns. Emphasis has been placed on the use of new or existing Fourier transform infrared (FTIR)-based systems with potential for field or tank deployment to perform in situ remote waste characterization. Near-infrared diffuse reflectance and mid-infrared attenuated total reflectance fiber optic probes coupled to a Bio-Rad FTS 60A spectrometry system have been evaluated. The near-infrared diffuse reflectance fiber probe system has also been used for preliminary screening of the moisture content and chemical composition of actual Hanford Site waste tank waste core samples. The attributes of this method for analyzing actual radioactive waste are discussed

Abrasion Resistance and Mechanical Properties of Waste-Glass-Fiber-Reinforced Roller-compacted Concrete

Science.gov (United States)

Yildizel, S. A.; Timur, O.; Ozturk, A. U.

2018-05-01

The potential use of waste glass fibers in roller-compacted concrete (RCC) was investigated with the aim to improve its performance and reduce environmental effects. The research was focused on the abrasion resistance and compressive and flexural strengths of the reinforced concrete relative to those of reference mixes without fibers. The freeze-thaw resistance of RCC mixes was also examined. It was found that the use of waste glass fibers at a rate of 2 % increased the abrasion resistance of the RCC mixes considerably.

Hanford Waste Vitrification Plant: Preliminary description of waste form and canister

International Nuclear Information System (INIS)

Mitchell, D.E.

1986-01-01

In July 1985, the US Department of Energy's Office of Civilian Radioactive Waste Management established the Waste Acceptance Process as the means by which defense high-level waste producers, such as the Hanford Waste Vitrification Plant, will develop waste acceptance requirements with the candidate geologic repositories. A complete description of the Waste Acceptance Process is contained in the Preliminary Hanford Waste Vitrification Plant Waste Form Qualification Plan. The Waste Acceptance Process defines three documents that high-level waste producers must prepare as a part of the process of assuming that a high-level waste product will be acceptable for disposal in a geologic repository. These documents are the Description of Waste Form and Canister, Waste Compliance Plan, and Waste Qualification Report. This document is the Hanford Waste Vitrification Plant Preliminary Description of Waste Form and Canister for disposal of Neutralized Current Acid Waste. The Waste Acceptance Specifications for the Hanford Waste Vitrification Plant have not yet been developed, therefore, this document has been structured to corresponds to the Waste Acceptance Preliminary Specifications for the Defense Waste Processing Facility High-Level Waste Form. Not all of the information required by these specifications is appropriate for inclusion in this Preliminary Description of Waste Form and Canister. Rather, this description is limited to information that describes the physical and chemical characteristics of the expected high-level waste form. The content of the document covers three major areas: waste form characteristics, canister characteristics, and canistered waste form characteristics. This information will be used by the candidate geologic repository projects as the basis for preliminary repository design activities and waste form testing. Periodic revisions are expected as the Waste Acceptance Process progresses

Waste Immobilisation Plant (WIP), Trombay

International Nuclear Information System (INIS)

Kaushik, C.P.; Agarwal, K.

2017-01-01

Waste Immobilization Plant (WIP), Trombay is designed and constructed for the management of radioactive liquid wastes generated during reprocessing of spent nuclear fuel from research reactors at Bhabha Atomic Research Centre. In common with such facilities elsewhere, the objective here is to manage the wastes in such a way as to protect human health and the environment and to limit any burden on future generations. The plant has several facilities for the handling and treatment of the three classes of waste, viz., high, intermediate and low level, a classification based on their radioactivity content. In keeping with the general objective of radioactive waste management, the focus is on concentration and confinement of radioactivity. Strict adherence to the universal principles of radiation protection during operation of the plant ensures that radiation exposure is always kept as low as reasonably achievable (ALARA) under the prescribed limits

Hanford Waste Vitrification Plant technology progress

International Nuclear Information System (INIS)

Wolfe, B.A.; Scott, J.L.; Allen, C.R.

1989-10-01

The Hanford Waste Vitrification Plant (HWVP) is currently being designed to safely process and temporarily store immobilized defense liquid high-level wastes from the Hanford Site. These wastes will be immobilized in a borosilicate glass waste form in the HWVP and stored onsite until a qualified geologic waste repository is ready for permanent disposal. Because of the diversity of wastes to be disposed of, specific technical issues are being addressed so that the plant can be designed and operated to produce a waste form that meets the requirements for permanent disposal in a geologic repository. This paper reports the progress to date in addressing these issues. 2 figs., 3 tabs

NOVEL USE OF WASTE KERATIN AND COTTON LINTER FIBERS FOR PROTOTYPE TISSUE PAPERS AND THEIR EVALUATION

Directory of Open Access Journals (Sweden)

Bo Shi

2010-05-01

Full Text Available Corporate environmental sustainability calls for sustainable product manufacturing with less creation of waste material or increased reuse of waste materials. One example is the use of keratin fiber from the poultry industry and cotton linter from the textile industry for paper and tissue manufacturing. In this paper, the feasibility of using these waste fibers to make paper was demonstrated in handsheets. The properties of these handsheets were compared to the properties of handsheets made with standard bleached eucalyptus tropical hardwood fibers. A blend of cotton linter and keratin fibers at 80/20 and 60/40 ratios showed a 59% and 73% improvement in sheet bulk, respectively, compared to eucalyptus handsheets. Similarly, air permeability of the cotton / keratin fiber handsheets improved 414% and 336%, respectively, versus the eucalyptus. However, the tensile index of the cotton and keratin fiber blends was lower than the eucalyptus sheets. There was no remarkable difference in water absorbency up to 20% keratin fiber. Above 20% of keratin fibers the water absorbency started to decrease, which is likely attributable to the hydrophobic nature of the protein-based keratin fiber.

Bonded carbon or ceramic fiber composite filter vent for radioactive waste

Science.gov (United States)

Brassell, Gilbert W.; Brugger, Ronald P.

1985-02-19

Carbon bonded carbon fiber composites as well as ceramic or carbon bonded ceramic fiber composites are very useful as filters which can separate particulate matter from gas streams entraining the same. These filters have particular application to the filtering of radioactive particles, e.g., they can act as vents for containers of radioactive waste material.

Separation efficiency of two waste polymer fibers for oily water treatment

OpenAIRE

Sokolović Dunja S.; Vulić Tatjana J.; Kiralj Arpad I.; Hadnađev-Kostić Milica S.; Sokolović Srđan S.

2016-01-01

This work is concerned with the efficiency of two different waste polymeric materials as the filter media in a laboratory-scale bed coalescer in the horizontal fluid flow mode, operating in a steady-state regime. The applied materials are: waste polyethylene terephthalate from textile industry, BA1 and waste polypropylene from carpet industry, PP. Using these compressible fiber polymeric materials, high bed porosity (up to 98%) could be obtained. The invest...

Conflicts concerning sites for waste treatment and waste disposal plants

International Nuclear Information System (INIS)

Werbeck, N.

1993-01-01

The erection of waste treatment and waste disposal flants increasingly meets with the disapproval of local residents. This is due to three factors: Firstly, the erection and operation of waste treatment plants is assumed to necessarily entail harmful effects and risks, which may be true or may not. Secondly, these disadvantages are in part considered to be non-compensable. Thirdly, waste treatment plants have a large catchment area, which means that more people enjoy their benefits than have to suffer their disadvantages. If residents in the vicinity of such plants are not compensated for damage sustained or harmed in ways that cannot be compensated for it becomes a rational stance for them, while not objecting to waste treatment and waste disposal plants in principle to object to their being in their own neighbourhood. The book comprehensively describes the subject area from an economic angle. The causes are analysed in detail and an action strategy is pointed, out, which can help to reduce acceptance problems. The individual chapters deal with emissions, risk potentials, optimization calculus considering individual firms or persons and groups of two or more firms or persons, private-economy approaches for the solving of site selection conflicts, collective decision-making. (orig./HSCH) [de

Waste management in MOX fuel fabrication plants

International Nuclear Information System (INIS)

Schneider, V.

1982-01-01

After a short description of a MOX fuel fabrication plant's activities the waste arisings in such a plant are discussed according to nature, composition, Pu-content. Experience has shown that proper recording leads to a reduction of waste arisings by waste awareness. Aspects of the treatment of α-waste are given and a number of treatment processes are reviewed. Finally, the current waste management practice and the α-waste treatment facility under construction at ALKEM are outlined. (orig./RW)

AVLIS production plant waste management plan

International Nuclear Information System (INIS)

1984-01-01

Following the executive summary, this document contains the following: (1) waste management facilities design objectives; (2) AVLIS production plant wastes; (3) waste management design criteria; (4) waste management plan description; and (5) waste management plan implementation. 17 figures, 18 tables

Extraction and characterization of natural cellulose fibers from maize tassel

CSIR Research Space (South Africa)

Maepa, CE

2015-04-01

Full Text Available This article reports on the extraction and characterization of novel natural cellulose fibers obtained from the maize (tassel) plant. Cellulose was extracted from the agricultural residue (waste biomaterial) of maize tassel. The maize tassel fibers...

Waste Isolation Pilot Plant transuranic wastes experimental characterization program: executive summary

International Nuclear Information System (INIS)

Molecke, M.A.

1978-11-01

A general overview of the Waste Isolation Pilot Plant transuranic wastes experimental characterization program is presented. Objectives and outstanding concerns of this program are discussed. Characteristics of transuranic wastes are also described. Concerns for the terminal isolation of such wastes in a deep bedded salt facility are divided into two phases, those during the short-term operational phase of the facility, and those potentially occurring in the long-term, after decommissioning of the repository. An inclusive summary covering individual studies, their importance to the Waste Isolation Pilot Plant, investigators, general milestones, and comments are presented

Renewable High-Performance Fibers from the Chemical Recycling of Cotton Waste Utilizing an Ionic Liquid.

Science.gov (United States)

Asaadi, Shirin; Hummel, Michael; Hellsten, Sanna; Härkäsalmi, Tiina; Ma, Yibo; Michud, Anne; Sixta, Herbert

2016-11-23

A new chemical recycling method for waste cotton is presented that allows the production of virgin textile fibers of substantially higher quality than that from the mechanical recycling methods that are used currently. Cotton postconsumer textile wastes were solubilized fully in the cellulose-dissolving ionic liquid 1,5-diazabicyclo[4.3.0]non-5-enium acetate ([DBNH]OAc) to be processed into continuous filaments. As a result of the heterogeneous raw material that had a different molar mass distribution and degree of polymerization, pretreatment to adjust the cellulose degree of polymerization by acid hydrolysis, enzyme hydrolysis, or blending the waste cotton with birch prehydrolyzed kraft pulp was necessary to ensure spinnability. The physical properties of the spun fibers and the effect of the processing parameters on the ultrastructural changes of the fibers were measured. Fibers with a tenacity (tensile strength) of up to 58 cN tex -1 (870 MPa) were prepared, which exceeds that of native cotton and commercial man-made cellulosic fibers. © 2016 Wiley-VCH Verlag GmbH & Co. KGaA, Weinheim.

Self-Shrinkage Behaviors of Waste Paper Fiber Reinforced Cement Paste considering Its Self-Curing Effect at Early-Ages

Directory of Open Access Journals (Sweden)

Zhengwu Jiang

2016-01-01

Full Text Available The aim of this paper was to study how the early-age self-shrinkage behavior of cement paste is affected by the addition of the waste paper fibers under sealed conditions. Although the primary focus was to determine whether the waste paper fibers are suitable to mitigate self-shrinkage as an internal curing agent under different adding ways, evaluating their strength, pore structure, and hydration properties provided further insight into the self-cured behavior of cement paste. Under the wet mixing condition, the waste paper fibers could mitigate the self-shrinkage of cement paste and, at additions of 0.2% by mass of cement, the waste paper fibers were found to show significant self-shrinkage cracking control while providing some internal curing. In addition, the self-curing efficiency results were analyzed based on the strength and the self-shrinkage behaviors of cement paste. Results indicated that, under a low water cement ratio, an optimal dosage and adding ways of the waste paper fibers could enhance the self-curing efficiency of cement paste.

Waste Isolation Pilot Plant Overview

Energy Technology Data Exchange (ETDEWEB)

Weaver, Douglas James [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-03-27

The mission of Waste Isolation Pilot Plant (WIPP) is to demonstrate the safe, environmentally sound, cost effective, permanent disposal of Transuranic (TRU) waste left from production of nuclear weapons.

Waste from decommissioning of nuclear power plants

International Nuclear Information System (INIS)

Nielsen, P.O.

1992-05-01

This report is based on the assumption that all twelve nuclear power plants will be shut down no later than A.D. 2010, as was decided by the parliament after the referendum on the future of nuclear power in Sweden. The recent 'Party agreement on the energy policy' of January 15, 1991 does, indeed, leave the door open for an extension of the operational period for the nuclear reactors. This will, however, not change the recommendations and conclusions drawn in this report. The report consists of two parts. Part 1 discusses classification of waste from decommissioning and makes comparisons with the waste arising from reactor operation. Part 2 discusses the documentation required for decommissioning waste. Also this part of the report draws parallels with the documentation required by the authorities for the radioactive waste arising from operation of the nuclear power plants. To some extent these subjects depend on the future use of the nuclear power plant sites after decommissioning of the plants. The options for future site use are briefly discussed in an appendix to the report. There are many similarities between the waste from reactor operations and the waste arising from dismantling and removal of decommissioned nuclear power plants. Hence it seems natural to apply the same criteria and recommendations to decommissioning waste as those presently applicable to reactor waste. This is certainly true also with respect to documentation, and it is strongly recommended that the documentation requirements on decommissioning waste are made identical, or at least similar, to the documentation requirements for reactor waste in force today. (au)

ORNL process waste treatment plant modifications

International Nuclear Information System (INIS)

Bell, J.P.

1982-01-01

The ORNL Process Waste Treatment Plant removes low levels of radionuclides (primarily Cs-137 and Sr-90) from process waste water prior to discharge. The previous plant operation used a scavenging precipitaton - ion exchange process which produced a radioactive sludge. In order to eliminate the environmental problems associated with sludge disposal, the plant is being converted to a new ion exchange process without the precipitation process

Y-12 Plant waste minimization strategy

International Nuclear Information System (INIS)

Kane, M.A.

1987-01-01

The 1984 Amendments to the Resource Conservation and Recovery Act (RCRA) mandate that waste minimization be a major element of hazardous waste management. In response to this mandate and the increasing costs for waste treatment, storage, and disposal, the Oak Ridge Y-12 Plant developed a waste minimization program to encompass all types of wastes. Thus, waste minimization has become an integral part of the overall waste management program. Unlike traditional approaches, waste minimization focuses on controlling waste at the beginning of production instead of the end. This approach includes: (1) substituting nonhazardous process materials for hazardous ones, (2) recycling or reusing waste effluents, (3) segregating nonhazardous waste from hazardous and radioactive waste, and (4) modifying processes to generate less waste or less toxic waste. An effective waste minimization program must provide the appropriate incentives for generators to reduce their waste and provide the necessary support mechanisms to identify opportunities for waste minimization. This presentation focuses on the Y-12 Plant's strategy to implement a comprehensive waste minimization program. This approach consists of four major program elements: (1) promotional campaign, (2) process evaluation for waste minimization opportunities, (3) waste generation tracking system, and (4) information exchange network. The presentation also examines some of the accomplishments of the program and issues which need to be resolved

ORGANIC WASTE USED IN AGRICULTURAL BIOGAS PLANTS

OpenAIRE

Joanna Kazimierowicz

2014-01-01

Treatment of organic waste is an ecological and economical problem. Searching method for disposal of these wastes, interest is methane fermentation. The use of this process in agricultural biogas plants allows disposal of hazardous waste, obtaining valuable fertilizer, while the production of ecologically clean fuel – biogas. The article presents the characteristics of organic waste from various industries, which make them suitable for use as substrates in agricultural biogas plants.

Development of waste water reuse water system for power plants

Energy Technology Data Exchange (ETDEWEB)

Park, K K; Kim, D H; Weon, D Y; Yoon, S W; Song, H R [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

1998-12-31

1. Status of waste water discharge at power plants 2. Present status of waste water reuse at power plants 3. Scheme of waste water reuse at power plants 4. Standardization of optimum system for waste water reuse at power plants 5. Establishment of low cost zero discharge system for waste water 6. Waste water treatment technology of chemical cleaning. (author). 132 figs., 72 tabs.

Development of waste water reuse water system for power plants

Energy Technology Data Exchange (ETDEWEB)

Park, K.K.; Kim, D.H.; Weon, D.Y.; Yoon, S.W.; Song, H.R. [Korea Electric Power Research Institute, Taejeon (Korea, Republic of)

1997-12-31

1. Status of waste water discharge at power plants 2. Present status of waste water reuse at power plants 3. Scheme of waste water reuse at power plants 4. Standardization of optimum system for waste water reuse at power plants 5. Establishment of low cost zero discharge system for waste water 6. Waste water treatment technology of chemical cleaning. (author). 132 figs., 72 tabs.

Process, product, and waste-stream monitoring with fiber optics

International Nuclear Information System (INIS)

Milanovich, F.P.; Hirschfeld, T.

1983-07-01

Fiber optic technology, motivated by communications and defense applications, has advanced significantly the past ten years. In particular, advances have been made in visible radiation transmission efficiency with concurrent reductions in fiber size, weight, and cost. Researchers at the Lawrence Livermore National Laboratory (LLNL) coupled these advances in fiber optic technology with analytical fluorescence analysis to establish a new technology - remote fiber fluorimetry (RFF). Laser-based RFF offers the potential to measure and monitor from one central and remote laboratory, on-line, and in near real time, trace (ppM) to substantial (g/L) concentrations of selected chemical species in typical process, product, and waste streams. The fluorimeter consists of a fluorescence or Raman spectrometer; unique coupling optics that separates input excitation (laser) radiation from return (fluorescence) radiation; a fiber optic cable; and an optrode - a terminal that interfaces the fiber to the measurement point, which is designed to respond quantitatively to a particular chemical species. At LLNL, research is underway into optrodes that measure pressure, temperature, and pH and those that detect and quantify various actinides, sulfates, inorganic chloride, hydrogen sulfide, aldehydes, and alcohols

Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification

International Nuclear Information System (INIS)

1993-08-01

The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program

ORGANIC WASTE USED IN AGRICULTURAL BIOGAS PLANTS

Directory of Open Access Journals (Sweden)

Joanna Kazimierowicz

2014-04-01

Full Text Available Treatment of organic waste is an ecological and economical problem. Searching method for disposal of these wastes, interest is methane fermentation. The use of this process in agricultural biogas plants allows disposal of hazardous waste, obtaining valuable fertilizer, while the production of ecologically clean fuel – biogas. The article presents the characteristics of organic waste from various industries, which make them suitable for use as substrates in agricultural biogas plants.

Safety in waste management plants: An Indian perspective

International Nuclear Information System (INIS)

Shekhar, P.; Ozarde, P.D.; Gandhi, P.M.

2000-01-01

Assurance of safety of public and plant workers and protection of the environment are prime objectives in the design and construction of Waste Management Plants. In India, waste management principles and strategies have been evolved in accordance with national and international regulations and standards for radiation protection. The regulations governing radiation protection have a far-reaching impact on the management of the radioactive waste. The wastes arise at each stages of the fuel cycle with varying chemical nature, generation rate and specific activity levels depending upon the type of the facility. Segregation of waste based on its chemical nature and specific activity levels is an essential feature, as its aids in selection of treatment and conditioning process. Selection of the process, equipment and materials in the plant, are governed by safety consideration alongside factors like efficiency and simplicity. The plant design considerations like physical separation, general arrangement, ventilation zoning, access control, remote handling, process piping routing, decontamination etc. have major role in realizing waste safety. Stringent quality control measures during all stages of construction have helped in achieving the design intended safety. These aspects together with operating experience gained form basis for the improved safety features in the design and construction of waste management plants. The comprehensive safety is derived from adoption of waste management strategies and appropriate plant design considerations. The paper briefly brings safety in waste management programme in India, in its current perspective. (author)

The Immobilisation of Krom and Stronsium Waste Using Natural Fiber Reinforced Cement

International Nuclear Information System (INIS)

Susetyo Haria Putero; Nunung Prabaningrum; Widya Rosita

2007-01-01

Cementation of hazardous liquid waste is one of the methods to minimize its detrimental effect on the environmental quality and human health. This research purpose was to study the effect of natural fiber composition and temperature on quality of the cement block reinforced by coconut (Cocos nucifera) fiber and bamboo (Bambusa vulgaris) fiber. This research was pursued by adsorbing stronsium waste and krom using zeolite. Thirteen percent volume of zeolite was mixed with 0.3 of water/cement ratio. Composition of natural fiber was varied by 0.00v/o, 0.05v/o, 0.10v/o, 0.25v/o, 0.50v/o, 0.75v/o and 1.00v/o. The cement blocks produced were heated at 0℃, 50℃, 100℃, 150℃, 200℃ and 250℃ for 10 minutes and then determined their compressive strength and leaching rate. The optimum composition of natural fiber causing increasing of mechanical strength has been founded at 0.50% v/o of fiber. On that composition the axial force resistance of fiber is higher than the radial one. The hydration reaction completely works when cement block is heated until certain temperature that results in the increasing of its compressive strength. However, the compressive strength of cement block heated up to 250℃ is still beyond the standard. Based on its compressive strength, the bamboo (Bambusa vulgaris) fiber is more feasible than coconut (Cocos nucifera) fiber for reinforcing cement block. Heating just influences on the physics properties of cement block. But, the ability of block cement to immobilize a matter is affected by properties of matters. (author)

WIPP: Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1984-01-01

The following aspects of the Waste Isolation Pilot Plant are discussed briefly: history and site selection; salt as a disposal medium; transporting waste materials; early key events; impacts on New Mexico; project organization; and site certification profile

Non-woven Textile Materials from Waste Fibers for Cleanup of Waters Polluted with Petroleum and Oil Products

Science.gov (United States)

Neznakomova, Margarita; Boteva, Silvena; Tzankov, Luben; Elhag, Mohamed

2018-04-01

The aim of this work was to investigate the possibility of using non-woven materials (NWM) from waste fibers for oil spill cleanup and their subsequent recovery. Manufacture of textile and readymade products generates a significant amount of solid waste. A major part of it is deposited in landfills or disposed of uncontrollably. This slowly degradable waste causes environmental problems. In the present study are used two types of NWM obtained by methods where waste fibers are utilized. Thus, real textile products are produced (blankets) with which spills are covered and removed by adsorption. These products are produced by two methods: the strengthening of the covering from recovered fibers is made by entanglement when needles of special design pass through layers (needle-punching) or by stitching with thread (technology Maliwatt). Regardless of the random nature of the fiber mixture, the investigated products are good adsorbents of petroleum products. The nature of their structure (a significant void volume and developed surface) leads to a rapid recovery of the spilled petroleum products without sinking of the fiber layer for the sampled times. The used NWM can be burned under special conditions.

Waste processing system for nuclear power plant

International Nuclear Information System (INIS)

Higashinakagawa, Emiko; Tezuka, Fuminobu; Maesawa, Yukishige; Irie, Hiromitsu; Daibu, Etsuji.

1996-01-01

The present invention concerns a waste processing system of a nuclear power plant, which can reduce the volume of a large amount of plastics without burying them. Among burnable wastes and plastic wastes to be discarded in the power plant located on the sea side, the plastic wastes are heated and converted into oils, and the burnable wastes are burnt using the oils as a fuel. The system is based on the finding that the presence of Na 2 O, K 2 O contained in the wastes catalytically improves the efficiency of thermal decomposition in a heating atmosphere, in the method of heating plastics and converting them into oils. (T.M.)

UTILIZATION OF MINERAL FIBER WASTE IN THE PRODUCTION OF GYPSUM PRODUCTS

Directory of Open Access Journals (Sweden)

Solov'ev Vitaliy Nikolaevich

2018-01-01

Full Text Available Subject: the effectiveness of using compositions with the use of basalt fibers is proven, but the composition must be selected depending on the binder and additives chosen. Research objectives: we examine the possibility of waste recycling of basalt fiber production during manufacturing of modified gypsum composite material with improved characteristics. Materials and methods: as a raw material, a gypsum binder of Samara production was used. As a reinforcement additive, a disperse waste of basalt fiber production of Tver region was used. Studying characteristics of the gypsum binder and modified mixture, and also comparative analysis of these characteristics by average density, total porosity, strength in compression and flexure of the gypsum composite were carried out using standard techniques. Results: dependence of physical and mechanical properties of the modified gypsum material on the content of the basalt fiber additive is established. It was found that an increase in concentration of the additive requires an increased water content or additional use of plasticizer. Conclusions: modification of gypsum stone with a mineral basalt additive will increase the strength, density and durability of thin-walled gypsum products, and, consequently, the demand for products due to ensuring their high quality in transportation and installation.

STUDY ON WASTE WATER TREATMENT PLANTS

Directory of Open Access Journals (Sweden)

Mariana DUMITRU

2015-04-01

Full Text Available Biogas is more and more used as an alternative source of energy, considering the fact that it is obtained from waste materials and it can be easily used in cities and rural communities for many uses, between which, as a fuel for households. Biogas has many energy utilisations, depending on the nature of the biogas source and the local demand. Generally, biogas can be used for heat production by direct combustion, electricity production by fuel cells or micro-turbines, Combined Hest and Power generation or as vehicle fuel. In this paper we search for another uses of biogas and Anaerobe Digestion substrate, such as: waste water treatment plants and agricultural wastewater treatment, which are very important in urban and rural communities, solid waste treatment plants, industrial biogas plants, landfill gas recovery plants. These uses of biogas are very important, because the gas emissions and leaching to ground water from landfill sites are serious threats for the environment, which increase more and more bigger during the constant growth of some human communities. That is why, in the developed European countries, the sewage sludge is treated by anaerobe digestion, depending on national laws. In Romania, in the last years more efforts were destined to use anaerobe digestion for treating waste waters and management of waste in general. This paper can be placed in this trend of searching new ways of using with maximum efficiency the waste resulted in big communities.

Hanford Waste Vitrification Plant

International Nuclear Information System (INIS)

Larson, D.E.; Allen, C.R.; Kruger, O.L.; Weber, E.T.

1991-10-01

The Hanford Waste Vitrification Plant (HWVP) is being designed to immobilize pretreated Hanford high-level waste and transuranic waste in borosilicate glass contained in stainless steel canisters. Testing is being conducted in the HWVP Technology Development Project to ensure that adapted technologies are applicable to the candidate Hanford wastes and to generate information for waste form qualification. Empirical modeling is being conducted to define a glass composition range consistent with process and waste form qualification requirements. Laboratory studies are conducted to determine process stream properties, characterize the redox chemistry of the melter feed as a basis for controlling melt foaming and evaluate zeolite sorption materials for process waste treatment. Pilot-scale tests have been performed with simulated melter feed to access filtration for solids removal from process wastes, evaluate vitrification process performance and assess offgas equipment performance. Process equipment construction materials are being selected based on literature review, corrosion testing, and performance in pilot-scale testing. 3 figs., 6 tabs

Hanford Waste Vitrification Plant technical manual

Energy Technology Data Exchange (ETDEWEB)

Larson, D.E. [ed.; Watrous, R.A.; Kruger, O.L. [and others

1996-03-01

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version.

Hanford Waste Vitrification Plant technical manual

International Nuclear Information System (INIS)

Larson, D.E.; Watrous, R.A.; Kruger, O.L.

1996-03-01

A key element of the Hanford waste management strategy is the construction of a new facility, the Hanford Waste Vitrification Plant (HWVP), to vitrify existing and future liquid high-level waste produced by defense activities at the Hanford Site. The HWVP mission is to vitrify pretreated waste in borosilicate glass, cast the glass into stainless steel canisters, and store the canisters at the Hanford Site until they are shipped to a federal geological repository. The HWVP Technical Manual (Manual) documents the technical bases of the current HWVP process and provides a physical description of the related equipment and the plant. The immediate purpose of the document is to provide the technical bases for preparation of project baseline documents that will be used to direct the Title 1 and Title 2 design by the A/E, Fluor. The content of the Manual is organized in the following manner. Chapter 1.0 contains the background and context within which the HWVP was designed. Chapter 2.0 describes the site, plant, equipment and supporting services and provides the context for application of the process information in the Manual. Chapter 3.0 provides plant feed and product requirements, which are primary process bases for plant operation. Chapter 4.0 summarizes the technology for each plant process. Chapter 5.0 describes the engineering principles for designing major types of HWVP equipment. Chapter 6.0 describes the general safety aspects of the plant and process to assist in safe and prudent facility operation. Chapter 7.0 includes a description of the waste form qualification program and data. Chapter 8.0 indicates the current status of quality assurance requirements for the Manual. The Appendices provide data that are too extensive to be placed in the main text, such as extensive tables and sets of figures. The Manual is a revision of the 1987 version

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

Extraction of zirconium from simulated acidic nitrate waste using liquid membrane in hollow fiber contactor

International Nuclear Information System (INIS)

Pandey, G.; Chinchale, R.; Renjith, A.U.; Dixit, S.; Mukhopadhyay, S.; Shenoy, K.T.; Ghosh, S.K.

2015-01-01

The acidic waste raffinate stream of zirconium (Zr) purification plant contains about 2 gpl of Zr in about 2M free nitric acid. TBP, which is the most commonly used solvent in the nuclear industry, is not suitable for the extraction of Zr from this lean solution as its distribution coefficient is less than one. In house synthesized Mixed Alkyl Phosphine Oxide (MAPO) is a potential extractant for Zr from this lean stream. Intensification of this process for recovery of Zr has been attempted through use of efficient contactor, namely, hollow fiber module and efficient process, namely, simultaneous extraction and stripping across liquid membrane containing MAPO. Based on batch equilibrium studies selection of suitable concentration of extractant, composition of diluent, selection and concentration of strippant for the proposed liquid membrane system was made. The selected organic and strippant concentration was used to study suitability of application of Dispersion Liquid Membrane (DLM) in hollow fiber contactor for recovery Zr from solution simulated to Zr plant raffinate. Challenges related to stable operation of the liquid membrane system like stability of the organic phase in the micropores of lumen and stability of the dispersion during the pertraction were addressed through pressure balance across the lumen and choice of adequate dispersion condition respectively. (author)

Sustainable waste management: Waste to energy plant as an alternative to landfill

International Nuclear Information System (INIS)

Cucchiella, Federica; D’Adamo, Idiano; Gastaldi, Massimo

2017-01-01

Highlights: • WTE plant is a reasonable and sustainable alternative technology to landfill. • A 150 kt plant in the only electrical configuration for Abruzzo region. • The percentage of energy recovery ranges from 21% to 25% in examined scenarios. • Financial Net Present Value is equal to 25.4 € per kiloton of treated waste. • The annual reduction of emissions is equal to 370 kgCO_2eq per ton of treated waste. - Abstract: The management of municipal solid waste (MSW) has been identified as one of the global challenges that must be carefully faced in order to achieve sustainability goals. European Union (EU) has defined as Waste to Energy (WTE) technology is able to create synergies with EU energy and climate policy, without compromising the achievement of higher reuse and recycling rates. The methodology used in this paper is based on two levels. A strategy analysis defines the amount of waste to incinerate with energy recovery considering different approaches based on unsorted waste, landfilled waste and separated collection rate, respectively. Consequently, it is evaluated the sustainability of a WTE plant as an alternative to landfill for a specific area. Two indicators are used: the Reduction of the Emissions of equivalent Carbon Dioxide (ER_C_O_2_e_q) and Financial Net Present Value (FNPV). Furthermore, a social analysis is conducted through interviews to identify the most critical elements determining the aversion toward the WTE realization. The obtained results show the opportunity to realize a 150 kt plant in the only electrical configuration. In fact, the cogenerative configuration reaches better environmental performances, but it is not profitable for this size. Profits are equal to 25.4 € per kiloton of treated waste and 370 kgCO_2eq per ton of treated waste are avoided using a WTE plant as an alternative to landfill. In this way, the percentage of energy recovery ranges from 21% to 25% in examined scenarios and disposal waste is minimised

Report: environmental assessment of Darmstadt (Germany) municipal waste incineration plant.

Science.gov (United States)

Rimaityte, Ingrida; Denafas, Gintaras; Jager, Johannes

2007-04-01

The focus of this study was the emissions from waste incineration plants using Darmstadt (Germany) waste incineration plant as an example. In the study the emissions generated by incineration of the waste were considered using three different approaches. Initially the emissions from the waste incineration plant were assessed as part of the impact of waste management systems on the environment by using a Municipal Solid Waste Management System (MSWMS) assessment tool (also called: LCA-IWM assessment tool). This was followed by a comparison between the optimal waste incineration process and the real situation. Finally a comparison was made between the emissions from the incineration plant and the emissions from a vehicle.

Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan

International Nuclear Information System (INIS)

Randklev, E.H.

1993-06-01

The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented

Recovery and removal of uranium by using plant wastes

International Nuclear Information System (INIS)

Nakajima, Akira; Sakaguchi, Takashi

1990-01-01

The uranium-adsorbing abilities of seven plant wastes were investigated. High abilities to adsorb uranium from non-saline water containing 10 mg dm -3 of uranium were observed with a number of plant wastes tested. However, with seawater supplemented with 10 mg dm -3 of uranium, similar results were found only with chestnut residues. When the plant wastes were immobilized with formaldehyde, their ability to adsorb uranium was increased. Uranium and copper ions were more readily adsorbed by all plant wastes tested than other metal ions from a solution containing a mixture of seven different heavy metals. The selective adsorption of heavy metal ions differs with different species of plant wastes. The immobilization of peanut inner skin, orange peel and grapefruit peel increased the selectivity for uranium. (author)

Bare Fiber Bragg Gratings embedded into concrete buffer Supercontainer concept for nuclear waste storage [ANIMMA--2015-IO-337

Energy Technology Data Exchange (ETDEWEB)

Kinet, Damien; Chah, Karima; Megret, Patrice; Caucheteur, Christophe [University of Mons, Boulevard Dolez 31, 7000 Mons (Belgium); Gusarov, Andrei [SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Faustov, Alexey [University of Mons, Boulevard Dolez 31, 7000 Mons (Belgium); SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Areias, Lou [Department Mechanics of Materials and Constructions - MeMC, Vrije Universiteit Brussel, Pleinlaan 2, 1050 Brussels (Belgium); EIG EURIDICE - European Underground Research Infrastructure for Disposal of nuclear waste In Clay Environment, Boeretang 200, 2400 Mol (Belgium)

2015-07-01

Nuclear power plants have been generating electricity for more than 50 years. In Belgium, 55% of the current energy supply comes from nuclear power. Providing for the safe storage of nuclear waste, including spent fuel (SF) and vitrified high level radioactive waste (HLW), remains an important challenge in the life cycle of nuclear fuel. In this context, the Belgian Agency for Radioactive Waste and Enriched Fissile Materials (ONDRAF/NIRAS) is investigating a reference conceptual design called the Supercontainer (SC) for the packaging of SF and HLW. This conceptual design is based on a multiple-barrier system consisting of a hermetically-sealed carbon steel overpack and a surrounding highly-alkaline concrete buffer. The first one is developed to retain the radionuclides. The two main functions of the buffer are (a) to create a high pH environment around the carbon steel overpack in order to passivate the metal surface and so to slow down the corrosion propagation during the thermal phase and (b) to provide a radiological shielding during the construction and the handling of the Supercontainer. A recent test has been performed to investigate the feasibility to construct the SC. This test incorporated several kinds of sensors including Digital Image Correlation (DIC), Acoustic Emission (AE), corrosion sensing techniques and optical fibers with and without fiber Bragg gratings (FBGs). In particular, several single-mode optical fibers with 4 mm long FBGs with different Bragg wavelengths and distributed along the optical fibers were used. For casting and curing condition monitoring, a number of gratings were incorporated inside the concrete buffer during the first stage of construction. Then other sensors were embedded near a heat source installed in the second stage to simulate the effects of heat generated by radioactive waste. The FBGs were designed to measure both temperature and strain effects in the concrete. To discriminate between these effects special packaging

Renewable energy in Switzerland - Potential of waste-water treatment plants, waste-incineration plants and drinking water supply systems - Strategical decisions in politics

International Nuclear Information System (INIS)

Kernen, M.

2006-01-01

This article discusses how waste-water treatment plants, waste-incineration plants and drinking water supply systems make an important contribution to the production of renewable energy in Switzerland. Financing by the 'Climate-Cent' programme, which finances projects involving the use of renewable energy, is discussed. Figures are quoted on the electrical energy produced in waste-water treatment plants, waste-incineration plants and combined heat and power generation plant. Eco-balances of the various systems are discussed. Political efforts being made in Switzerland, including the 'Climate Cent', are looked at and promotion provided by new energy legislation is discussed. Eco-power and the processing of sewage gas to meet natural gas quality standards are discussed, as are energy analysis, co-operation between various research institutions and external costs

Radioactive waste management for German nuclear power plants

International Nuclear Information System (INIS)

Weh, R.; Methling, D.; Sappok, M.

1996-01-01

In Germany, back-end fuel cycle provisions must be made for the twenty nuclear power plants currently run by utilities with an aggregate installed power of 23.4 GWe, and the four nuclear power plants already shut down. In addition, there are the shut down nuclear power plants of the former German Democratic Republic, and a variety of decommissioned prototype nuclear power plants built with the participation of the federal government and by firms other than utilities. The nuclear power plants operated by utilities contribute roughly one third of the total electricity generation in public power plants, thus greatly ensuring a stable energy supply in Germany. The public debate in Germany, however, focuses less on the good economic performance of these plants, and the positive acceptance at their respective sites, but rather on their spent fuel and waste management which, allegedly, is not safe enough. The spent fuel and waste management of German nuclear power plants is planned on a long-term basis, and executed in a responsible way by proven technical means, in the light of the provisions of the Atomic Act. Each of the necessary steps of the back end of the fuel cycle is planned and licensed in accordance with German nuclear law provisions. The respective facilities are built, commissioned, and monitored in operation with the dedicated assistance of expert consultants and licensing authorities. Stable boundary conditions are a prerequisite in ensuring the necessary stability in planning and running waste management schemes. As producers of waste, nuclear power plants are responsible for safe waste management and remain the owners of that waste until it has been accepted by a federal repository. (orig./DG) [de

Waste-to-energy plants - a solution for a cleaner future

International Nuclear Information System (INIS)

Pfeiffer, J.

2007-01-01

Waste-to-energy plants reduce the municipal solid waste volume by about 80% and convert it into residue. The residue quality naturally depends on the burned waste quality and also on the combustion parameters. Hence, tighter control of the plant can improve the residue quality. The generated combustion energy is regarded as renewable energy and is typically used to feed a turbine to generate electricity. Waste-to-energy furnaces react slowly on changing waste charge, so they are not used for peak load generation. The generated electrical power is a plant by product and is sold as base load generation. Usually the waste is burned on a grate which limits the plant size to about 160,000 tons of waste per year or 20 tons of waste per hour or about 28 MW. More recent technology utilizes fluidized bed combustion, which allows larger plant sizes up to 50 MW. Due to the unknown waste composition and stringent environmental standards involved, waste-to-energy plants employ sophisticated flue gas cleaning devices for emission control. ABB's Performance Monitoring continuously compares actual plant and equipment performance to expected performance. This includes the on-line calculation of the waste calorific heat allowing operator decision support and automated control system responses. Dedicated reports offer detailed data on operations, maintenance and emissions to plant management staff. ABB combustion optimization solutions use model based predictive control techniques to reliably find the most suitable set-points for improving the heat rate and reducing emissions like NO x . (author)

Waste management at the Ardennes power plant

International Nuclear Information System (INIS)

Abraham, J.P.

1979-01-01

In 1976, the SENA (with the participation of EDF, CEA and CEC in the framework of a research program on the management and storage of radioactive wastes) has developed an industrial pilot plant for the encapsulation of wastes in thermosetting polyester resins. The industrial putting in operation of the plant will enable most of the wastes from the nuclear station to be processed. The quality of products will be improved and the volume and processing cost reduced

Waste management in reprocessing plants

International Nuclear Information System (INIS)

Mortreuil, M.

1982-01-01

This lecture will give a survey of the French policy for the management of wastes in reprocessing plants. In consideration of their radioactivity, they must be immobilized in matrix in such a manner that they are stored under optimal safety conditions. A general review on the nature, nucleide content and quantity of the various wastes arising from thermal nuclear fuel reprocessing is given in the light of the French plants UP1 at Marcoule and UP2 at La Hague. The procedures of treatment of such wastes and their conditioning into inert packages suitable for temporary or terminal storage are presented, especially concerning the continuous vitrification process carried out for fission product solutions. The requirements of each option are discussed and possible alternative solutions are exposed. (orig./RW)

Disposal of radioactive wastes from Czechoslovak nuclear power plants

International Nuclear Information System (INIS)

Neumann, L.

In gaseous radioactive waste disposal, aerosol particles are filtered and gaseous wastes are discharged in the environment. The filters and filter materials used are stored on solid radioactive waste storage sites in the individual power plants. Liquid radioactive wastes are concentrated and the concentrates are stored. Distillates and low-level radioactive waste water are discharged into the hydrosphere. Solid radioactive wastes are stored without treatment in power plant bunkers. Bituminization and cementation of liquid radioactive wastes are discussed. (H.S.)

Processing and solidification of Savannah River Plant high-level waste

International Nuclear Information System (INIS)

Kelley, J.A.

1981-01-01

The entire flowsheet for processing and solidification of Savannah River Plant (SRP) high-level wastes has been demonstrated. A new small-scale integrated pilot plant is operating with actual radioactive wastes, and large-scale equipment is being demonstrated with nonradioactive simulated wastes. Design of a full-scale waste solidification plant is in progress. Plant construction is expected to begin in 1983, and startup is anticipated in 1988. The plant will poduce about 500 cans of glass per year with each can containing about 1.5 tons of glass

Hanford Waste Vitrification Plant applied technology plan

International Nuclear Information System (INIS)

Kruger, O.L.

1990-09-01

This Applied Technology Plan describes the process development, verification testing, equipment adaptation, and waste form qualification technical issues and plans for resolution to support the design, permitting, and operation of the Hanford Waste Vitrification Plant. The scope of this Plan includes work to be performed by the research and development contractor, Pacific Northwest Laboratory, other organizations within Westinghouse Hanford Company, universities and companies with glass technology expertise, and other US Department of Energy sites. All work described in this Plan is funded by the Hanford Waste Vitrification Plant Project and the relationship of this Plan to other waste management documents and issues is provided for background information. Work to performed under this Plan is divided into major areas that establish a reference process, develop an acceptable glass composition envelope, and demonstrate feed processing and glass production for the range of Hanford Waste Vitrification Plant feeds. Included in this work is the evaluation and verification testing of equipment and technology obtained from the Defense Waste Processing Facility, the West Valley Demonstration Project, foreign countries, and the Hanford Site. Development and verification of product and process models and other data needed for waste form qualification documentation are also included in this Plan. 21 refs., 4 figs., 33 tabs

Management of radioactive waste from reprocessing plants

International Nuclear Information System (INIS)

Kanwar Raj

2010-01-01

Reprocessing and recycling of both fissile and fertile components back into appropriate reactor systems is an integral part of three stage nuclear energy programme of India. Different steps involved in processing of spent nuclear fuel (SNF) are decladding, dissolution and recovery of fissile and fertile materials. Reprocessing of SNF is a complex process involving handling of large quantity of radioactive materials and processing chemicals. There are three reprocessing plants in operation in the country at Trombay, Tarapur and Kalpakkam. Out of these plants, Trombay reprocessing plant is engaged in reprocessing of SNF from research reactors and other two plants are processing of SNF from PHWRs. A facility is being built for reprocessing of thorium based spent fuel at BARC, Trombay based on the experience of pilot plant scale. Like other industrial activities of nuclear fuel cycle, fuel reprocessing facilities too generate various types of radioactive waste streams. These are generated in all the three physical forms namely solid, liquid and gas. These waste streams are primarily categorized on the basis of concentration of radionuclides, their half lives and toxicity. Management of these wastes aims at (a) recovery and recycle of useful materials, (b) concentration and confinement of radioactivity in inert and stable matrices, (c) minimization of final waste volume for disposal, (d) decontamination of effluents following ALARA principle and (e) minimization of radioactive discharge to the environment. The present paper outlines the salient features of management of different types of radioactive waste generated in reprocessing plants handling SNF from research reactors and PHWR

Incorporation of waste and fiber kaolin caroa panels in Medium Density Fiberboard - MDF

International Nuclear Information System (INIS)

Bezerra, A.F.C.; Santana, L.N.L.; Neves, G.A.; Carvalho, L.H. de; Lopes, F.F.M.

2012-01-01

Medium-density panels are composites molded under high temperature and pressure which have physical and mechanical properties similar to those of solid wood. Their composition includes eucalyptus grandis fibers and pinus elliotii fibers, but other fibers can be used such as caroa fibers. The goal of this work was to manufacture panels which kaolin waste and caroa fibers and compare their physical, chemical and mechanical of these panels with a others. Both residue and the fibers were characterized by: differential thermal analysis, thermal gravimetric analysis and Xray diffraction. Through the process of pressing the test specimens were fabricated, test samples were evaluated by three point bending, internal bond, water absorption and swelling in thickness. The samples have low levels of thickness swelling, flexural strength and higher tensile and absorption content relative to commercial MDF. (author)

Solid Waste from the Operation and Decommissioning of Power Plants

Energy Technology Data Exchange (ETDEWEB)

Brown, Marilyn Ann [Georgia Inst. of Technology, Atlanta, GA (United States); D' Arcy, Daniel [Georgia Inst. of Technology, Atlanta, GA (United States); Lapsa, Melissa Voss [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sharma, Isha [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Li, Yufei [Georgia Inst. of Technology, Atlanta, GA (United States)

2017-01-05

This baseline report examines the solid waste generated by the U.S. electric power industry, including both waste streams resulting from electricity generation and wastes resulting from the decommissioning of power plants. Coal and nuclear plants produce large volumes of waste during electricity generation, and this report describes the policies and procedures for handling these materials. Natural gas and oil-fired power plants face similar waste challenges. Renewables considered in this baseline report include hydropower, wind and solar.

Acceptable knowledge document for INEEL stored transuranic waste - Rocky Flats Plant waste. Revision 2

International Nuclear Information System (INIS)

1998-01-01

This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems

Acceptable knowledge document for INEEL stored transuranic waste -- Rocky Flats Plant waste. Revision 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-23

This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems.

Irradiation Effects of Electron Beam on Optical Fibers

Energy Technology Data Exchange (ETDEWEB)

Kim, Jin Kyu; Cho, Gyu Seong [KAIST, Daejeon (Korea, Republic of); Choi, Hong Gu; Oh, Kyung Hwan [Yonsei University, Seoul (Korea, Republic of); Cho, Ho Jin [Nucron Co. Ltd., Seoul (Korea, Republic of)

2009-10-15

The surveillance or monitoring systems used in space station, nuclear power plant and nuclear waste repository, are often equipped with optical fibers to remotely locating expensive camera systems so as to protect them from direct irradiation. Especially in nuclear power plant and nuclear waste repository, irradiation by gamma-ray and beta-ray are most concerned. The effective life-time of such surveillance system may depend on the soundness of the optical fiber because it is the component to be exposed the high intensity of radiation field by purpose. Though the degradation of mechanical properties such as hardness and elasticity may occur but the degradation of the optical property such as spectral transmittance is the most possible cause of the effective life-time limitation. Generally 30 % reduction of light signal transmittance is considered as the life-time threshold point of such optical systems. In this paper, we studied irradiation effects on spectral transparency of various commonly-used optical fibers with high energy electron beam to conveniently simulate the both gamma-ray and beta-ray irradiation situation.

Biogas plants: Utilization of microorganisms for waste management

Energy Technology Data Exchange (ETDEWEB)

Stadlbauer, E A; Trieu, C

1984-05-01

The continuous realisation of the basic principles of environmental conservation and compatability demands concern about the problems of eliminating wastes in an industrialised society. Biogas- and therefore technical plants for methane generation by anaerobic fermentation have promoted to effective means of environmental protection and sources of alternate energy from organic wastes. Methane fermentation has been employed for the stabilisation of sludges at municipal waste treatment plants for decades. However, the anaerobic digestion process shows promising applications both for industrial effluents and agricultural wastes as well as municipal solid wastes and covered waste deposits. In view of the advances achieved interdisciplinary cooperation the actual potential and perspective of methane fermentation technology with respect to the solution of the increasing problems of waste management and energy supply is discussed.

Activated Carbon Fibers with Hierarchical Nanostructure Derived from Waste Cotton Gloves as High-Performance Electrodes for Supercapacitors

Science.gov (United States)

Wei, Chao; Yu, Jianlin; Yang, Xiaoqing; Zhang, Guoqing

2017-06-01

One of the most challenging issues that restrict the biomass/waste-based nanocarbons in supercapacitor application is the poor structural inheritability during the activating process. Herein, we prepare a class of activated carbon fibers by carefully selecting waste cotton glove (CG) as the precursor, which mainly consists of cellulose fibers that can be transformed to carbon along with good inheritability of their fiber morphology upon activation. As prepared, the CG-based activated carbon fiber (CGACF) demonstrates a surface area of 1435 m2 g-1 contributed by micropores of 1.3 nm and small mesopores of 2.7 nm, while the fiber morphology can be well inherited from the CG with 3D interconnected frameworks created on the fiber surface. This hierarchically porous structure and well-retained fiber-like skeleton can simultaneously minimize the diffusion/transfer resistance of the electrolyte and electron, respectively, and maximize the surface area utilization for charge accumulation. Consequently, CGACF presents a higher specific capacitance of 218 F g-1 and an excellent high-rate performance as compared to commercial activated carbon.

Activated Carbon Fibers with Hierarchical Nanostructure Derived from Waste Cotton Gloves as High-Performance Electrodes for Supercapacitors.

Science.gov (United States)

Wei, Chao; Yu, Jianlin; Yang, Xiaoqing; Zhang, Guoqing

2017-12-01

One of the most challenging issues that restrict the biomass/waste-based nanocarbons in supercapacitor application is the poor structural inheritability during the activating process. Herein, we prepare a class of activated carbon fibers by carefully selecting waste cotton glove (CG) as the precursor, which mainly consists of cellulose fibers that can be transformed to carbon along with good inheritability of their fiber morphology upon activation. As prepared, the CG-based activated carbon fiber (CGACF) demonstrates a surface area of 1435 m 2  g -1 contributed by micropores of 1.3 nm and small mesopores of 2.7 nm, while the fiber morphology can be well inherited from the CG with 3D interconnected frameworks created on the fiber surface. This hierarchically porous structure and well-retained fiber-like skeleton can simultaneously minimize the diffusion/transfer resistance of the electrolyte and electron, respectively, and maximize the surface area utilization for charge accumulation. Consequently, CGACF presents a higher specific capacitance of 218 F g -1 and an excellent high-rate performance as compared to commercial activated carbon.

In situ chemical characterization of waste sludges using FTIR-based fiber optic sensors

International Nuclear Information System (INIS)

Rebagay, T.V.; Dodd, D.A.; Jeppson, D.W.; Lockrem, L.L.; Blewett, G.R.

1994-02-01

The characterization of unknown mixed wastes is a mandatory step in today's climate of strict environmental regulations. Cleaning up the nuclear and chemical wastes that have accumulated for 50 years at the Hanford Site is the largest single cleanup task in the United States today. The wastes are stored temporarily in carbon steel single- and double-shell tanks that are buried in tank farms at the Site. In the 1950s, a process to scavenge radioactive cesium and other soluble radionuclides in the wastes was developed to create additional tank space for waste storage. This scavenging process involved treatment of the wastes with alkali cyanoferrates and nickel sulfate to precipitate 137 Cs in the presence of nitrate oxidant. Recent safety issues have focused on the stability of cyanoferrate-bearing wastes with large quantities of nitrates and nitrites. Nitrate has been partially converted to nitrite as a result of radiolysis during more than 35 years of storage. The major safety issue is the possibility of the presence of local hot spots enriched in 137 Cs and 90 Sr that under optimum conditions can self-heat causing dry out and a potential runaway reaction of the cyanoferrates with the nitrates/nitrites). For waste tank safety, accurate data of the concentration and distribution of cyanoferrates in the tanks are needed. Because of the extensive sampling required and the highly restricted activities allowed in the tank farms, simulated tank wastes are used to provide an initial basis for identifying and quantifying realistic concerns prior to waste remediation. Fiber optics provide a tool for the remote and in situ characterization of hazardous and toxic materials. This study is focused on near-infrared (NIR) and mid-infrared (MIR) fiber optic sensors for in situ chemical characterization of Hanford Site waste sludges

Pilot incineration plant for solid, combustible, and low-level wastes

International Nuclear Information System (INIS)

Francioni, W.M.

Radioactively contaminated wastes are formed in the handling of radioactive materials at the Federal Institute for Reactor Research (FIRR) and in other facilities, hospitals, sanitoria, industry, and nuclear power plants. A large part of the wastes are combustible and only very slightly radioactive. Incineration of these wastes is obvious. A pilot incineration plant, henceforth called the PIP, for radioactive combustible wastes of the FIRR is surveyed. The plant and its individual components are described. The production costs of the plant and experience gained in operation available at present are reviewed. Solid combustible radioactive waste can be incinerated in the PIP. The maximum possible reduction in volume of these wastes is achieved by incineration. Subsequently the chemically sterile ashes can be consolidated in a stable block suitable for long-term storage mixing with cement

Waste water treatment plants as sources of polyfluorinated compounds, polybrominated diphenyl ethers and musk fragrances to ambient air

International Nuclear Information System (INIS)

Weinberg, Ingo; Dreyer, Annekatrin; Ebinghaus, Ralf

2011-01-01

To investigate waste water treatment plants (WWTPs) as sources of polyfluorinated compounds (PFCs), polybrominated diphenyl ethers (PBDEs) and synthetic musk fragrances to the atmosphere, air samples were simultaneously taken at two WWTPs and two reference sites using high volume samplers. Contaminants were accumulated on glass fiber filters and PUF/XAD-2/PUF cartridges, extracted compound-dependent by MTBE/acetone, methanol, or hexane/acetone and detected by GC-MS or HPLC-MS/MS. Total (gas + particle phase) concentrations ranged from 97 to 1004 pg m -3 (neutral PFCs), -3 (ionic PFCs), 5781 to 482,163 pg m -3 (musk fragrances) and -3 (PBDEs) and were usually higher at WWTPs than at corresponding reference sites, revealing that WWTPs can be regarded as sources of musk fragrances, PFCs and probably PBDEs to the atmosphere. Different concentrations at the two WWTPs indicated an influence of WWTP size or waste water origin on emitted contaminant amounts. - Waste water treatment plants can be regarded as sources of musk fragrances, polyfluorinated compounds (PFCs) and polybrominated diphenyl ethers (PBDEs) to the atmosphere

Aqueous Waste Treatment Plant at Aldermaston

International Nuclear Information System (INIS)

Keene, D.; Fowler, J.; Frier, S.

2006-01-01

For over half a century the Pangbourne Pipeline formed part of AWE's liquid waste management system. Since 1952 the 11.5 mile pipeline carried pre-treated wastewater from the Aldermaston site for safe dispersal in the River Thames. Such discharges were in strict compliance with the exacting conditions demanded by all regulatory authorities, latterly, those of the Environment Agency. In March 2005 AWE plc closed the Pangbourne Pipeline and ceased discharges of treated active aqueous waste to the River Thames via this route. The ability to effectively eliminate active liquid discharges to the environment is thanks to an extensive programme of waste minimization on the Aldermaston site, together with the construction of a new Waste Treatment Plant (WTP). Waste minimization measures have reduced the effluent arisings by over 70% in less than four years. The new WTP has been built using best available technology (evaporation followed by reverse osmosis) to remove trace levels of radioactivity from wastewater to exceptionally stringent standards. Active operation has confirmed early pilot scale trials, with the plant meeting throughput and decontamination performance targets, and final discharges being at or below limits of detection. The performance of the plant allows the treated waste to be discharged safely as normal industrial effluent from the AWE site. Although the project has had a challenging schedule, the project was completed on programme, to budget and with an exemplary safety record (over 280,000 hours in construction with no lost time events) largely due to a pro-active partnering approach between AWE plc and RWE NUKEM and its sub-contractors. (authors)

Hanford Waste Vitrification Plant quality assurance program description: Overview and applications

International Nuclear Information System (INIS)

Caplinger, W.H.

1990-12-01

This document describes the Hanford Waste Vitrification Plant Project Quality Assurance Program. This program is being implemented to ensure the acceptability of high-level radioactive canistered waste forms produced by the Hanford Waste Vitrification Plant for disposal in a licensed federal repository. The Hanford Waste Vitrification Plant Quality Assurance Program is comprised of this Quality Assurance Program Description as well as the associated contractors' quality assurance programs. The objective of this Quality Assurance Program Description is to provide the Hanford Waste Vitrification Plant Project participants with guidance and direction for program implementation while satisfying the US Department of Energy Office of Civilian Radioactive Waste Management needs in repository licensing activities with regard to canistered waste forms. To accomplish this objective, this description will be prepared in three parts: Part 1 - Overview and applications document; Part 2 - Development and qualification of the canistered waste form; Part 3 - Production of canistered waste forms. Part 1 describes the background, strategy, application, and content of the Hanford Waste Vitrification Plant Quality Assurance Program. This Quality Assurance Program Description, when complete, is designed to provide a level of confidence in the integrity of the canistered waste forms. 8 refs

Waste Treatment & Immobilization Plant Project

Data.gov (United States)

Federal Laboratory Consortium — In southeastern Washington State, Bechtel National, Inc. is designing, constructing and commissioning the world's largest radioactive waste treatment plant for the...

Development of a testing method for asbestos fibers in treated materials of asbestos containing wastes by transmission electron microscopy

Energy Technology Data Exchange (ETDEWEB)

Yamamoto, Takashi, E-mail: tyama@nies.go.jp [Center for Material Cycles and Waste Management Research, National Institute for Environmental Studies, 16-2 Onogawa, Tsukuba, Ibaraki 305-8506 (Japan); Kida, Akiko [Faculty of Agriculture, Ehime University, 3-5-7 Tarumi, Matsuyama, Ehime 790-8566 (Japan); Noma, Yukio [Department of Environmental Science, Fukuoka Womens University, 1-1-1 Kasumigaoka, Higashiku, Fukuoka 813-8529 (Japan); Terazono, Atsushi [Center for Material Cycles and Waste Management Research, National Institute for Environmental Studies, 16-2 Onogawa, Tsukuba, Ibaraki 305-8506 (Japan); Sakai, Shin-ichi [Environmental Preservation Research Center, Kyoto University, Yoshidahonmachi, Sakyoku, Kyoto 606-8501 (Japan)

2014-02-15

Highlights: • A high sensitive and selective testing method for asbestos in treated materials of asbestos containing wastes was developed. • Asbestos can be determined at a limits are a few million fibers per gram and a few μg g{sup −1}. • High temperature melting treatment samples were determined by this method. Asbestos fiber concentration were below the quantitation limit in all samples, and total fiber concentrations were determined as 47–170 × 10{sup 6} g{sup −1}. - Abstract: Appropriate treatment of asbestos-containing wastes is a significant problem. In Japan, the inertization of asbestos-containing wastes based on new treatment processes approved by the Minister of the Environment is promoted. A highly sensitive method for testing asbestos fibers in inertized materials is required so that these processes can be approved. We developed a method in which fibers from milled treated materials are extracted in water by shaking, and are counted and identified by transmission electron microscopy. Evaluation of this method by using asbestos standards and simulated slag samples confirmed that the quantitation limits are a few million fibers per gram and a few μg/g in a sample of 50 mg per filter. We used this method to assay asbestos fibers in slag samples produced by high-temperature melting of asbestos-containing wastes. Fiber concentrations were below the quantitation limit in all samples, and total fiber concentrations were determined as 47–170 × 10{sup −6} f/g. Because the evaluation of treated materials by TEM is difficult owing to the limited amount of sample observable, this testing method should be used in conjunction with bulk analytical methods for sure evaluation of treated materials.

Savannah River Plant Separations Department mixed waste program

International Nuclear Information System (INIS)

Wierzbicki, W.M.

1988-01-01

The Department of Energy's (DOE) Savannah River Plant (SRP) generates radioactive and mixed waste as a result of the manufacture of nuclear material for the national defense program. The radioactive portion of the mixed waste and all nonhazardous radioactive wastes would continue to be regulated by DOE under the Atomic Energy Act. The Separations Department is the largest generator of solid radioactive waste at the Savannah River Plant. Over the last three years, the Separations Department has developed and implemented a program to characterize candidate mixed-waste streams. The program consisted of facility personnel interviews, a waste-generation characterization program and waste testing to determine whether a particular waste form was hazardous. The Separations Department changed waste-handling practices and procedures to meet the requirements of the generator standards. For each Separation Department Facility, staging areas were established, inventory and reporting requirements were developed, operating procedures were revised to ensure proper waste handling, and personnel were provided hazardous waste training. To emphasize the importance of the new requirements, a newsletter was developed and issued to all Separations supervisory personnel

Calcium Ion Removal by KMnO4 Modified Pineapple Leaf Waste Carbon Prepared from Waste of Pineapple Leaf Fiber Production Processing

Directory of Open Access Journals (Sweden)

Sumrit Mopoung

2016-12-01

Full Text Available Pineapple leaf fiber waste carbon, modified with 3% KMnO4, was used for Ca2+ removal from aqueous solution. The effects of contact time, loading, water hardness, and isotherms on Ca2+ adsorption were studied. The results show that the Ca2+ ion removal by pineapple leaf fiber waste carbon could be improved by modification with KMnO4. The adsorption would reach equilibrium state at about 60 min for a water source with hardness values of 40-200 mg/dm3. Increases in total hardness (40 to 200 mg/dm3 lead to a decrease in Ca2+ ion removal efficiency (90.05% to 37.65% and an increase in Ca2+ ion adsorption capacity at equilibrium (4.37 mg/g to 8.95 mg/g. The Ca2+ removal efficiencies increase with increasing loading of modified waste carbon. The equilibrium data were fitted well by both the Langmuir isotherm and the Freundlich isotherm. For the Langmuir isotherm model, the values of the maximum Ca2+ adsorption capacity and Langmuir constant being 2.81 mg/g and 0.9262 dm3 /g, respectively. On the other hand for the Freundlich isotherm model, the KF and n values are 1.374 dm3 (1/n mg (1-1/n/g and 4.671, respectively. These results indicate that modified pineapple fiber waste carbon is a material with high Ca2+ ion adsorption capacity, heterogeneity, and high affinity.

New Mexico waste plant sits idle amid controversy

International Nuclear Information System (INIS)

Lovejoy, L.A. Jr.

1994-01-01

The Department of Energy (DOE) hopes to permanently dispose of radioactive waste from its weapons program at a Waste Isolation Pilot Plant about 26 miles from Carlsbad, New Mexico. The plant has been plagued by problems, according to Lindsay A. Lovejoy, Jr., an assistant attorney general of New Mexico. Among them are cracks in the walls of some of the underground rooms slated for storage of radioactive waste. Meanwhile, above-ground problems involve DOE's struggle toward regulatory compliance. The Environmental Protection Agency (EPA), under the Resource Conservation Recovery Act, has assumed a regulatory role over DOE's radioactive waste-disposal efforts, which is a new role for the agency. Lovejoy proposes that EPA, in its regulation of the New Mexico plant, develop compliance criteria and involve DOE and the public in ongoing open-quotes dialogue aimed at ferreting out any and all problems before a single scrap of radioactive waste is deposited into the earth beneath new Mexico.close quotes

Production of bacterial cellulose and enzyme from waste fiber sludge

Science.gov (United States)

2013-01-01

Background Bacterial cellulose (BC) is a highly crystalline and mechanically stable nanopolymer, which has excellent potential as a material in many novel applications, especially if it can be produced in large amounts from an inexpensive feedstock. Waste fiber sludge, a residue with little or no value, originates from pulp mills and lignocellulosic biorefineries. A high cellulose and low lignin content contributes to making the fiber sludge suitable for bioconversion, even without a thermochemical pretreatment step. In this study, the possibility to combine production of BC and hydrolytic enzymes from fiber sludge was investigated. The BC was characterized using field-emission scanning electron microscopy and X-ray diffraction analysis, and its mechanical properties were investigated. Results Bacterial cellulose and enzymes were produced through sequential fermentations with the bacterium Gluconacetobacter xylinus and the filamentous fungus Trichoderma reesei. Fiber sludges from sulfate (SAFS) and sulfite (SIFS) processes were hydrolyzed enzymatically without prior thermochemical pretreatment and the resulting hydrolysates were used for BC production. The highest volumetric yields of BC from SAFS and SIFS were 11 and 10 g/L (DW), respectively. The BC yield on initial sugar in hydrolysate-based medium reached 0.3 g/g after seven days of cultivation. The tensile strength of wet BC from hydrolysate medium was about 0.04 MPa compared to about 0.03 MPa for BC from a glucose-based reference medium, while the crystallinity was slightly lower for BC from hydrolysate cultures. The spent hydrolysates were used for production of cellulase with T. reesei. The cellulase activity (CMCase activity) in spent SAFS and SIFS hydrolysates reached 5.2 U/mL (87 nkat/mL), which was similar to the activity level obtained in a reference medium containing equal amounts of reducing sugar. Conclusions It was shown that waste fiber sludge is a suitable raw material for production of

Use of diffusive optical fibers for plant lighting

Energy Technology Data Exchange (ETDEWEB)

Kozai, T.; Kitaya, Y.; Fujiwara, K. [Chiba Univ., Matsudo (Japan); Kino, S.; Kinowaki, M. [Topy Green Ltd., Tokyo (Japan)

1994-12-31

Lighting is one of the most critical aspects in plant production and environmental research with plants. Much research has been repeated on the effect of light intensity, spectral distribution of light and lighting cycle, but comparatively little research done on the effect of lighting direction on the growth, development and morphology of plants. When plants are grown with lamps above, light is directed downward to the plants. Downward or overhead lighting is utilized in almost all cases. However, downward lighting does not always give the best result in terms of lighting efficiency, growth, development and morphology of plants. Kitaya et al. (1988) developed a lighting system in which two rooting beds were arranged; one above and the other under fluorescent lamps. Lettuce plants grew normally in the lower bed and suspended upside-down under the upper bed. The lettuce plants suspended upside-down were given the light in upward direction (upward lighting). No significant difference in growth, development and morphology was found between the lettuce plants grown by the downward and upward lighting. Combining upward and downward lighting, improved spacing efficiency and reduced electricity cost per plant compared with conventional, downward lighting. From the above example, when designing a lighting system for plants with lamps more lighting direction should be considered. In the present study, a sideward lighting system was developed using diffusive optical fiber belts. More higher quality tissue-cultured transplants could be produced in reduced space with sideward lighting system than with a downward lighting system. An application of the sideward lighting system using diffusive optical fiber belts is described and advantages and disadvantages are discussed.

Preliminary Study on Impact Resistances of Fiber Reinforced Concrete Applied Nuclear Power Plants

International Nuclear Information System (INIS)

Jin, Byeong Moo; Kim, Young Jin; Jeon, Se Jin

2013-01-01

Studies to improve the impact resistance depending upon design parameters for fiber reinforced concrete, such as type of fibers and application ratio, are in progress. Authors assessed first the impact resistance of concrete walls depending upon fiber types and missile impact velocities. The safety assessment of nuclear power plants against large civil aircraft crashes have been accomplished for normal concrete and fiber reinforced concretes in this study. Studies on the safety assessments on the nuclear power plants against large civil aircraft crashes are ongoing actively. As a step of evaluating the applicability of fiber reinforced concrete in means of ensuring more structural safety of the nuclear power plants against impact, the impact resistance for the 1% steel and 2% polyamide fiber reinforced concretes have been evaluated. For reactor containment building structures, it seem there is no impact resistance enhancement of fiber reinforced concrete applied to reactor containment building in the cases of impact velocity 150 m/sec considered in this study. However this results from the pre-stressing forces which introduce compressive stresses in concrete wall and dome section of reactor containment building. Nonetheless there may be benefits to apply fiber reinforced concrete to nuclear power plants. For double containment type reactor containment building, the outer structure is a reinforced concrete structure. The impact resistances for non pre-stressed cylindrical reactor containment buildings are enhanced by 23 to 47 % for 2 % polyamide fiber reinforced concretes and 1 % steel fiber reinforced concretes respectively. For other buildings such as auxiliary building, compound building and fuel storage building surrounding the reactor containment building, there are so many reinforced concrete walls which are anticipated some enhancements of impact resistance by using fiber reinforced concretes. And heavier or faster large civil aircraft impacts produce higher

Preliminary Study on Impact Resistances of Fiber Reinforced Concrete Applied Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Jin, Byeong Moo; Kim, Young Jin; Jeon, Se Jin [Daewoo E and C Co. Ltd., Suwon (Korea, Republic of)

2013-10-15

Studies to improve the impact resistance depending upon design parameters for fiber reinforced concrete, such as type of fibers and application ratio, are in progress. Authors assessed first the impact resistance of concrete walls depending upon fiber types and missile impact velocities. The safety assessment of nuclear power plants against large civil aircraft crashes have been accomplished for normal concrete and fiber reinforced concretes in this study. Studies on the safety assessments on the nuclear power plants against large civil aircraft crashes are ongoing actively. As a step of evaluating the applicability of fiber reinforced concrete in means of ensuring more structural safety of the nuclear power plants against impact, the impact resistance for the 1% steel and 2% polyamide fiber reinforced concretes have been evaluated. For reactor containment building structures, it seem there is no impact resistance enhancement of fiber reinforced concrete applied to reactor containment building in the cases of impact velocity 150 m/sec considered in this study. However this results from the pre-stressing forces which introduce compressive stresses in concrete wall and dome section of reactor containment building. Nonetheless there may be benefits to apply fiber reinforced concrete to nuclear power plants. For double containment type reactor containment building, the outer structure is a reinforced concrete structure. The impact resistances for non pre-stressed cylindrical reactor containment buildings are enhanced by 23 to 47 % for 2 % polyamide fiber reinforced concretes and 1 % steel fiber reinforced concretes respectively. For other buildings such as auxiliary building, compound building and fuel storage building surrounding the reactor containment building, there are so many reinforced concrete walls which are anticipated some enhancements of impact resistance by using fiber reinforced concretes. And heavier or faster large civil aircraft impacts produce higher

Fiber from ramie plant (Boehmeria nivea): A novel suture biomaterial

Energy Technology Data Exchange (ETDEWEB)

Kandimalla, Raghuram; Kalita, Sanjeeb; Choudhury, Bhaswati [Drug discovery laboratory, Institute of Advanced Study in Science and Technology, Guwahati, Assam 781035 (India); Devi, Dipali [Seri biotech laboratory, Institute of Advanced Study in Science and Technology, Guwahati, Assam 781035 (India); Kalita, Dhaneswar [Government Ayurvedic College and Hospital, Jalukbari, Guwahati, Assam 781014 (India); Kalita, Kasturi [Department of Pathology, Hayat Hospital, Guwahati, Assam 781034 (India); Dash, Suvakanta [Girijananda Chowdhury Institute of pharmaceutical science, Azara, Guwahati, Assam 781017 (India); Kotoky, Jibon, E-mail: jkotoky@gmail.com [Drug discovery laboratory, Institute of Advanced Study in Science and Technology, Guwahati, Assam 781035 (India)

2016-05-01

The quest for developing an ideal suture material prompted our interest to develop a novel suture with advantageous characters to market available ones. From natural origin only silk, cotton and linen fibers are presently available in market as non-absorbable suture biomaterials. In this study, we have developed a novel, cost-effective, and biocompatible suture biomaterial from ramie plant, Boehmeria nivea fiber. Field emission scanning electron microscopy (FE-SEM), energy-dispersive X-ray spectroscopy (EDX), attenuated total reflection Fourier transform infrared spectroscopy (ATR-FTIR) and thermo gravimetric analysis (TGA) results revealed the physicochemical properties of raw and degummed ramie fiber, where the former one showed desirable characteristics for suture preparation. The braided multifilament ramie suture prepared from degummed fiber exhibited excellent tensile strength. The suture found to be biocompatible towards human erythrocytes and nontoxic to mammalian cells. The fabricated ramie suture exhibited significant antibacterial activity against Escherichia coli, Bacillus subtilis and Staphylococcus aureus; which can be attributed to the inherent bacteriostatic ability of ramie plant fiber. In vivo wound closure efficacy was evaluated in adult male wister rats by suturing the superficial wound incisions. Within seven days of surgery the wound got completely healed leaving no rash and scar. The role of the ramie suture in complete wound healing was supported by the reduced levels of serum inflammatory mediators. Histopathology studies confirmed the wound healing ability of ramie suture, as rapid synthesis of collagen, connective tissue and other skin adnexal structures were observed within seven days of surgery. Tensile properties, biocompatibility and wound closure efficacy of the ramie suture were comparable with market available BMSF suture. The outcome of this study can drive tremendous possibility for the utilization of ramie plant fiber for

Fiber from ramie plant (Boehmeria nivea): A novel suture biomaterial

International Nuclear Information System (INIS)

Kandimalla, Raghuram; Kalita, Sanjeeb; Choudhury, Bhaswati; Devi, Dipali; Kalita, Dhaneswar; Kalita, Kasturi; Dash, Suvakanta; Kotoky, Jibon

2016-01-01

The quest for developing an ideal suture material prompted our interest to develop a novel suture with advantageous characters to market available ones. From natural origin only silk, cotton and linen fibers are presently available in market as non-absorbable suture biomaterials. In this study, we have developed a novel, cost-effective, and biocompatible suture biomaterial from ramie plant, Boehmeria nivea fiber. Field emission scanning electron microscopy (FE-SEM), energy-dispersive X-ray spectroscopy (EDX), attenuated total reflection Fourier transform infrared spectroscopy (ATR-FTIR) and thermo gravimetric analysis (TGA) results revealed the physicochemical properties of raw and degummed ramie fiber, where the former one showed desirable characteristics for suture preparation. The braided multifilament ramie suture prepared from degummed fiber exhibited excellent tensile strength. The suture found to be biocompatible towards human erythrocytes and nontoxic to mammalian cells. The fabricated ramie suture exhibited significant antibacterial activity against Escherichia coli, Bacillus subtilis and Staphylococcus aureus; which can be attributed to the inherent bacteriostatic ability of ramie plant fiber. In vivo wound closure efficacy was evaluated in adult male wister rats by suturing the superficial wound incisions. Within seven days of surgery the wound got completely healed leaving no rash and scar. The role of the ramie suture in complete wound healing was supported by the reduced levels of serum inflammatory mediators. Histopathology studies confirmed the wound healing ability of ramie suture, as rapid synthesis of collagen, connective tissue and other skin adnexal structures were observed within seven days of surgery. Tensile properties, biocompatibility and wound closure efficacy of the ramie suture were comparable with market available BMSF suture. The outcome of this study can drive tremendous possibility for the utilization of ramie plant fiber for

Dechlorane Plus (DP) in air and plants at an electronic waste (e-waste) site in South China

Energy Technology Data Exchange (ETDEWEB)

Chen Shejun [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Tian Mi; Wang Jing; Shi Tian [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Graduate School, Chinese Academy of Sciences, Beijing 100049 (China); Luo Yong [Guangdong Forestry Survey and Planning Institute, Guangzhou 510520 (China); Luo Xiaojun [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China); Mai Bixian, E-mail: nancymai@gig.ac.cn [State Key Laboratory of Organic Geochemistry, Guangzhou Institute of Geochemistry, Chinese Academy of Sciences, Guangzhou 510640 (China)

2011-05-15

Air and foliage samples (Eucalyptus spp. and Pinus massoniana Lamb.) were collected from e-waste and reference sites in South China and analyzed for Dechlorane Plus (DP) and two dechlorinated DPs. DP concentrations in the air were 13.1-1794 pg/m{sup 3} for the e-waste site and 0.47-35.7 pg/m{sup 3} for the reference site, suggesting the recycling of e-waste is an important source of DP to the environment. Plant DP, with concentrations of 0.45-51.9 ng/g dry weight at the e-waste site and 0.09-2.46 ng/g at the reference site, exhibited temporal patterns similar to the air DP except for pine needle at the reference site. The air-plant exchange of DP could be described with the two-compartment model. Anti-Cl{sub 11} DP was measured in most air and plant samples from the e-waste site. The ratios of anti-Cl{sub 11} DP to anti-DP in the air and plants may indicate the preferential uptake of dechlorinated DP by plant compared with DP. - Highlights: > Dechlorane Plus was widely present in the air and plants in South China. > Temporal patterns of the plant DP could be described with the two-compartment model. > Plant uptake can efficiently reduce air DP concentration at the reference site. > Anti-Cl{sub 11} DP was measured in most air and plant samples from the e-waste site. - E-waste recycling in South China results in wide occurrence of DP in the air and plant.

Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification. Revision 3, Part 2

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program.

Mechanical compaction of Waste Isolation Pilot Plant simulated waste

International Nuclear Information System (INIS)

Butcher, B.M.; Thompson, T.W.; VanBuskirk, R.G.; Patti, N.C.

1991-06-01

The investigation described in this report acquired experimental information about how materials simulating transuranic (TRU) waste compact under axial compressive stress, and used these data to define a model for use in the Waste Isolation Pilot Plant (WIPP) disposal room analyses. The first step was to determine compaction curves for various simultant materials characteristic of TRU waste. Stress-volume compaction curves for various combinations of these materials were than derived to represent the combustible, metallic, and sludge waste categories. Prediction of compaction response in this manner is considered essential for the WIPP program because of the difficulties inherent in working with real (radioactive) waste. Next, full-sized 55-gallon drums of simulated combustible, metallic, and sludge waste were axially compacted. These results provided data that can be directly applied to room consolidation and data for comparison with the predictions obtained in Part 1 of the investigation. Compaction curves, which represent the combustible, metallic, and sludge waste categories, were determined, and a curve for the averaged waste inventory of the entire repository was derived. 9 refs., 31 figs., 12 tabs

Defense Waste Processing Facility, Savannah River Plant

International Nuclear Information System (INIS)

After 10 years of research, development, and testing, the US Department of Energy is building a new facility which will prepare high-level radioactive waste for permanent disposal. The Defense Waste Processing Facility, known as the DWPF, will be the first production-scale facility of its kind in the United States. In the DWPF, high-level waste produced by defense activities at the Savannah River Plant will be processed into a solid form, borosilicate glass, suitable for permanent off-site geologic disposal. With construction beginning in the fall of 1983, the DWPT is scheduled to be operational in 1989. By 2005, the DWPF will have immobilized the backlog of high-level waste which has been accumulating in storage tanks at the Savannah River Plant since 1954. Canisters of the immobilized waste will then be ready for permanent disposal deep under the ground, safely isolated from the environment

Managing nuclear waste from power plants

International Nuclear Information System (INIS)

Keeney, R.L.; Winterfeldt, D. von

1994-01-01

National strategies to manage nuclear waste from commercial nuclear power plants are analyzed and compared. The current strategy is to try to operate a repository at Yucca Mountain, Nevada, to dispose storage at a centralized facility or next to nuclear power plants. If either of these is pursued now, the analysis assumes that a repository will be built in 2100 for waste not subsequently put to use. The analysis treats various uncertainties: whether a repository at Yucca Mountain would be licensed, possible theft and misuse of the waste, innovations in repository design and waste management, the potential availability of a cancer cure by 2100, and possible future uses of nuclear waste. The objectives used to compare alternatives include concerns for health and safety, environmental and socioeconomic impacts, and direct economic costs, as well as equity concerns (geographical, intergenerational, and procedural), indirect economic costs, as well as equity concerns (geographical, intergenerational, and procedural), indirect economic costs to electricity ratepayers, federal government responsibility to manage nuclear waste, and implications of theft and misuse of nuclear waste. The analysis shows that currently building an underground repository at Yucca Mountain is inferior to other available strategies by the equivalent of $10,000 million to $50,000 million. This strongly suggests that this policy should be reconsidered. A more detailed analysis using the framework presented would help to define a new national policy to manage nuclear waste. 36 refs., 3 figs., 17 tabs

The effects of adding waste plastic fibers on some properties of roller compacted concrete

Directory of Open Access Journals (Sweden)

Abed Adil

2018-01-01

Full Text Available An attempt to produce of roller compacted concrete (RCC improved by adding waste plastic fibers (WPFs resulting from cutting the PET beverage bottles was recorded in this study. The method which is used for production of RCC is an approved design method for ACI committee (5R-207,1980[1]. WPF was added by volumetric percentages ranging between (0.5 to 2 % and reference concrete mix was produced for comparison reason. Many tests were conducted on the models produced by rolling compacted concrete like compressive strength, flexural strength, modulus of elasticity, dry density, water absorption and ultrasonic pulse velocity. The analysis of the results showed that the use of plastic waste fibers (1% had led to improvement in the properties of each of the compressive strength and flexural strength compared with reference concrete. Results also showed that the addition of these, fibers increase water absorption and reduce the speed of Ultrasonic pulse velocity.

Improvements of radioactive waste management at WWER nuclear power plants

International Nuclear Information System (INIS)

2006-04-01

This report is part of a systematic IAEA effort to improve waste management practices at WWER plants and to make them consistent with the current requirements and standards for safe and reliable operation of nuclear power plants. The report reviews the wet and dry solid waste management practices at the various types of WWER nuclear power plants (NPP) and describes approaches and recent achievements in waste minimization. Waste minimization practices in use at western PWRs are reviewed and compared, and their applicability at WWER plants is evaluated. Radioactive waste volume reduction issues and waste management practices are reflected in many IAEA publications. However, aspects of waste minimization specific to individual WWER nuclear power plant designs and WWER waste management policies are not addressed extensively in those publications. This report covers the important aspects applicable to the improvement of waste management at WWER NPP, including both plant-level and country-level considerations. It is recognized that most WWER plants are already implementing many of these concepts and recommendations with varying degrees of success; others will benefit from the included considerations. The major issues addressed are: - Review of current waste management policies and practices related to WWERs and western PWRs, including the influence of the original design concepts and significant modifications, liquid waste discharge limits and dry solid waste clearance levels applied in individual countries, national policies and laws, and other relevant aspects affecting the nature and quantities of waste arisings; - Identification of strategies and methods for improving the radioactive waste management generated in normal operation and maintenance at WWERs. This report is a composite (combination) of the two separate initiatives mentioned above. The first draft report was prepared at the meeting 26-30 May 1997 by five consultants. The draft was improved during an

Management of radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

1985-01-01

This Code of Practice defines the minimum requirements for the design and operation of structures, systems and components important for the management of radioactive wastes from thermal neutron nuclear power plants. The topics covered include design and operation of gaseous, liquid and solid waste systems, waste transport, storage and disposal, decommissioning wastes and wastes from unplanned events

Assessment of fiber optic sensors and other advanced sensing technologies for nuclear power plants

International Nuclear Information System (INIS)

Hashemian, H.M.

1996-01-01

As a result of problems such as calibration drift in nuclear plant pressure sensors and the recent oil loss syndrome in some models of Rosemount pressure transmitters, the nuclear industry has become interested in fiber optic pressure sensors. Fiber optic sensing technologies have been considered for the development of advanced instrumentation and control (I ampersand C) systems for the next generation of reactors and in older plants which are retrofitted with new I ampersand C systems. This paper presents the results of a six-month Phase I study to establish the state-of-the-art in fiber optic pressure sensing. This study involved a literature review, contact with experts in the field, an industrial survey, a site visit to a fiber optic sensor manufacturer, and laboratory testing of a fiber optic pressure sensor. The laboratory work involved both static and dynamic performance tests. This initial Phase I study has recently been granted a two-year extension by the U.S. Nuclear Regulatory Commission (NRC). The next phase will evaluate fiber optic pressure sensors in specific nuclear plant applications in addition to other advanced methods for monitoring critical nuclear plant equipment

Improving plant performance through efficient nuclear waste management - The French experience

International Nuclear Information System (INIS)

Peterson, C.H.

1986-01-01

This paper discusses high and low level waste management and its effect on Plant Performance. In France, high level waste policy is an improtant factor in plant performance. The LLW section of the paper discusses the role of French Industry organization as well as the benefits of standard plants with standard practices. The regulation of the production of waste and the waste processing by utilities is covered

Combined Multi-criteria Evaluation Stage Technique as an Agro Waste Evaluation Indicator for Polymeric Composites: Date Palm Fibers as a Case Study

Directory of Open Access Journals (Sweden)

Faris M. AL-Oqla

2014-06-01

Full Text Available The final features of natural fiber composites (NFCs depend on the integrated characteristics of their constituents. In the industry today, natural agro waste fibers are evaluated using a limited number of criteria. In this work, a combined multi-criteria evaluation stage technique (CMCEST is introduced as a simple efficient systematic indicator to enhance evaluation of the available natural agro wastes for polymeric composites. In this proposed technique, criteria affecting the proper selection of natural agro waste fibers were combined and divided into sequence stages as follows: single-evaluation-criterion (SEC, combined-double-evaluation-criterion (CDEC, combined-triple-evaluation-criterion (CTEC, etc. These stages are based on combined physical, mechanical, and economic evaluation criteria and can be extended to several further stages to include other beneficial characteristics. The effectiveness of this technique was demonstrated by evaluating coir, date palm, jute, hemp, kenaf, and oil palm fibers simultaneously. This combined evaluation criteria can lead to more informative decisions regarding selection of the most suitable fiber type for polymeric composites. The CMCEST enhancements can reveal new potential fiber types through better evaluation schemes, help achieve clearer indications of the capabilities of available agro wastes to enhance composites, and determine proper ecological waste management practices. Utilizing the proposed technique, the date palm fiber type was found to be quite promising due to beneficial characteristics revealed in CTEC, which provides a reasonable, cheap, and eco-friendly alternative material suitable for different applications.

Waste water pilot plant research, development, and demonstration permit application

International Nuclear Information System (INIS)

1993-03-01

This permit application has been prepared to obtain a research, development, and demonstration permit to perform pilot-scale treatability testing on the 242-A Evaporator process condensate waste water effluent stream. It provides the management framework, and controls all the testing conducted in the waste water pilot plant using dangerous waste. It also provides a waste acceptance envelope (upper limits for selected constituents) and details the safety and environmental protection requirements for waste water pilot plant testing. This permit application describes the overall approach to testing and the various components or requirements that are common to all tests. This permit application has been prepared at a sufficient level of detail to establish permit conditions for all waste water pilot plant tests to be conducted

Removal of cesium using coconut fiber in raw and modified forms for the treatment of radioactive liquid wastes

International Nuclear Information System (INIS)

Jesus, Nella N.M. de; Nobre, Vanessa B.; Potiens Junior, Ademar J.; Sakata, Solange K.; Di Vitta, Patricia B.

2013-01-01

Sorption is one of the most studied methods to reduce the volume of radioactive waste streams. Cesium-137 is a radioisotope formed by the fission of uranium and it can cause health problems due to its easy assimilation by cells. The aim of this study is to evaluate the potential of coconut fiber in removing cesium from radioactive liquid wastes; this process can help in disposing radioactive waste. The experiments were performed in batch and the particle size of the fiber ranged between 0.30 mm and 0.50 mm. The fiber was treated with hydrogen peroxide in alkaline medium. The following parameters were analyzed: contact time, pH and concentration of cesium ions in aqueous solution. After the experiments the samples were filtered and cesium remaining in solution was quantified by inductively coupled plasma optical emission spectrometry. (author)

Removal of cesium using coconut fiber in raw and modified forms for the treatment of radioactive liquid wastes

Energy Technology Data Exchange (ETDEWEB)

Jesus, Nella N.M. de; Nobre, Vanessa B.; Potiens Junior, Ademar J.; Sakata, Solange K., E-mail: sksakata@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Di Vitta, Patricia B. [Universidade de Sao Paulo (USP), SP (Brazil). Instituto de Quimica

2013-07-01

Sorption is one of the most studied methods to reduce the volume of radioactive waste streams. Cesium-137 is a radioisotope formed by the fission of uranium and it can cause health problems due to its easy assimilation by cells. The aim of this study is to evaluate the potential of coconut fiber in removing cesium from radioactive liquid wastes; this process can help in disposing radioactive waste. The experiments were performed in batch and the particle size of the fiber ranged between 0.30 mm and 0.50 mm. The fiber was treated with hydrogen peroxide in alkaline medium. The following parameters were analyzed: contact time, pH and concentration of cesium ions in aqueous solution. After the experiments the samples were filtered and cesium remaining in solution was quantified by inductively coupled plasma optical emission spectrometry. (author)

Management of abnormal radioactive wastes at nuclear power plants

International Nuclear Information System (INIS)

1989-01-01

As with any other industrial activity, a certain level of risk is associated with the operation of nuclear power plants and other nuclear facilities. That is, on occasions nuclear power plants or nuclear facilities may operate under conditions which were not specifically anticipated during the design and construction of the plant. These abnormal conditions and situations may cause the production of abnormal waste, which can differ in character or quantity from waste produced during normal routine operation of nuclear facilities. Abnormal waste can also occur during decontamination programmes, replacement of a reactor component, de-sludging of storage ponds, etc. The management of such kinds of waste involves the need to evaluate existing waste management systems in order to determine how abnormal wastes should best be handled and processed. There are no known publications on this subject, and the IAEA believes that the development and exchange of such information among its Member States would be useful for specialists working in the waste management area. The main objective of this report is to review existing waste management practices which can be applied to abnormal waste and provide assistance in the selection of appropriate technologies and processes that can be used when abnormal situations occur. Naturally, the subject of abnormal waste is complex and this report can only be considered as a guide for the management of abnormal waste. Refs, figs and tabs.

Phase I: the pipeline-gas demonstration plant. Demonstration plant engineering and design. Volume 18. Plant Section 2700 - Waste Water Treatment

Energy Technology Data Exchange (ETDEWEB)

None

1981-05-01

Contract No. EF-77-C-01-2542 between Conoco Inc. and the US Department of Energy provides for the design, construction, and operation of a demonstration plant capable of processing bituminous caking coals into clean pipeline quality gas. The project is currently in the design phase (Phase I). This phase is scheduled to be completed in June 1981. One of the major efforts of Phase I is the process and project engineering design of the Demonstration Plant. The design has been completed and is being reported in 24 volumes. This is Volume 18 which reports the design of Plant Section 2700 - Waste Water Treatment. The objective of the Waste Water Treatment system is to collect and treat all plant liquid effluent streams. The system is designed to permit recycle and reuse of the treated waste water. Plant Section 2700 is composed of primary, secondary, and tertiary waste water treatment methods plus an evaporation system which eliminates liquid discharge from the plant. The Waste Water Treatment Section is designed to produce 130 pounds per hour of sludge that is buried in a landfill on the plant site. The evaporated water is condensed and provides a portion of the make-up water to Plant Section 2400 - Cooling Water.

Radioactive-waste isolation pilot plant

International Nuclear Information System (INIS)

Weart, W.D.

1977-01-01

The objective of the Waste Isolation Pilot Plant (WIPP) program is to demonstrate the suitability of bedded salt, specifically, the bedded salt deposits in the Los Medanos area of southeastern New Mexico, as a disposal medium for radioactive wastes. Our program responsibilities include site selection considerations, all aspects of design and development, technical guidance of facility operation, environmental impact assessment, and technical support to ERDA for developing public understanding of the facility

Development of high integrity containers for rad-waste treatment

Energy Technology Data Exchange (ETDEWEB)

Song, Yung Chul; Cho, Myung Sug; Jung, Yun Sub [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

1995-12-31

Nuclear power plants are generating rad waste such as solid wastes, concentrated liquid wastes, spent resins and spent filters, and various types of imported containers which have different specifications and material properties are employed to handle the rad wastes according to facility characteristics of the plants or the type of wastes. These containers are stored at the intermediate storage facilities at the plant site due to the construction delay of permanent disposal site, and the additional construction of storage and disposal sites become more difficult with increase of the numbers and the operation time of the plants. In order to solve these difficulties, rad wastes volume reduction facilities such as High Pressure Compression Facility or Drying Facility are being installed and use of High Integrity Containers(HIC) are increasing. Therefore, we decide quality and technology standards required for the HIC, and then develop the HIC which satisfies the standards with new composite material called Steel Fiber Polymer Impregnated Concrete(SFPIC) (author). 84 refs., 118 figs.

Development of high integrity containers for rad-waste treatment

Energy Technology Data Exchange (ETDEWEB)

Song, Yung Chul; Cho, Myung Sug; Jung, Yun Sub [Korea Electric Power Corp. (KEPCO), Taejon (Korea, Republic of). Research Center

1996-12-31

Nuclear power plants are generating rad waste such as solid wastes, concentrated liquid wastes, spent resins and spent filters, and various types of imported containers which have different specifications and material properties are employed to handle the rad wastes according to facility characteristics of the plants or the type of wastes. These containers are stored at the intermediate storage facilities at the plant site due to the construction delay of permanent disposal site, and the additional construction of storage and disposal sites become more difficult with increase of the numbers and the operation time of the plants. In order to solve these difficulties, rad wastes volume reduction facilities such as High Pressure Compression Facility or Drying Facility are being installed and use of High Integrity Containers(HIC) are increasing. Therefore, we decide quality and technology standards required for the HIC, and then develop the HIC which satisfies the standards with new composite material called Steel Fiber Polymer Impregnated Concrete(SFPIC) (author). 84 refs., 118 figs.

Air filtration media from electrospun waste high-impact polystyrene fiber membrane

Science.gov (United States)

Zulfi, Akmal; Miftahul Munir, Muhammad; Hapidin, Dian Ahmad; Rajak, Abdul; Edikresnha, Dhewa; Iskandar, Ferry; Khairurrijal, Khairurrijal

2018-03-01

Nanofiber membranes were synthesized from waste high-impact polystyrene (HIPS) using electrospinning method and then applied as air filtration media. The waste HIPS precursor solution with the concentration of 20 wt.% was prepared by dissolving waste HIPS into the mixture of d-limonene and DMF solvents. Beaded or fine nanofibers could be achieved by adjusting the ratio of solvents mixture (d-limonene and DMF). Using the ratios of solvents (d-limonene: DMF) of 3:1, 1:1, and 1:3, it was obtained beaded HIPS nanofibers with the average diameter of 272 nm, beaded HIPS nanofibers with the average diameter of 937, and fine HIPS nanofibers with the average diameter of 621 nm, respectively. From the FTIR spectral analysis, it was found that the FTIR peaks of the HIPS nanofiber membranes are the same as those of the cleaned waste HIPS and there are no FTIR peaks of DMF and d-limonene solvents. These findings implied that the electrospinning process allows the recycling of waste HIPS into HIPS nanofibers without any trapped solvent phases or apparent degradation of the original material. From the contact angle measurement, it was confirmed that the HIPS nanofiber membranes are hydrophobic and the presence of the beads in the HIPS nanofiber membranes varies their contact angles. From the air-filtration test, it was shown that the fiber morphology (beaded or fine nanofibers) considerably affects the filtration performance of the membranes. The presence of beads increased the distance between the fibers so that the pressure drop decreased. Moreover, the basis weight of the membrane greatly affected the filtration efficiency. The HIPS nanofiber membrane with the basis weight of 12.22 g m‑2 had the efficiency greater than 99.999%, which was equivalent to that of the HEPA filter.

Incineration plant for low active waste at Inshass, LAWI

International Nuclear Information System (INIS)

Krug, W.; Thoene, L.; Schmitz, H.J.; Abdelrazek, I.D.

1993-10-01

The LAWI (Low Active Waste Incinerator) prototype incinerating plant was devised and constructed according to the principle of the Juelich thermoprocess and installed at the Egyptian research centre Inshass. In parallel, AEA Cairo devised and constructed their own operations building for this plant with all the features, infrastructural installations and rooms required for operating the plant and handling and treating low-level radioactive wastes. The dimensions of this incinerator were selected so as to be sufficient for the disposal of solid, weakly radioactive combustible wastes from the Inshass Research Centre and the environment (e.g. Cairo hospitals). (orig./DG) [de

Radioactive waste processing method for a nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Sugimoto, Y; Kuriyama, O

1976-06-04

Object is to subject radioactive liquid waste in a nuclear power plant to reverse permeation process after which it is vaporized and concentrated thereby decreasing the quantity of foam to be used to achieve effective concentration of the liquid waste. Liquid waste containing a radioactive material produced from a nuclear power plant is first applied with pressure in excess of osmotic pressure by a reverse permeation device and is separated into clean water and concentrated liquid by semi-permeable membrane. Next, the thus reverse-permeated and concentrated waste is fed to an evaporator which control foaming by the foam and then further reconcentrated for purification of the liquid waste.

Processing of transuranic waste at the Savannah River Plant

International Nuclear Information System (INIS)

Daugherty, B.A.; Gruber, L.M.; Mentrup, S.J.

1986-01-01

Transuranic wastes at the Savannah River Plant (SRP) have been retrievably stored on concrete pads since early 1972. This waste is stored primarily in 55-gallon drums and large carbon steel boxes. Higher activity drums are placed in concrete culverts. In support of a National Program to consolidate and permanently dispose of this waste, a major project is planned at SRP to retrieve and process this waste. This project, the TRU Waste Facility (TWF), will provide equipment and processes to retrieve TRU waste from 20-year retrievable storage and prepare it for permanent disposal at the Waste Isolation Pilot Plant (WIPP) geological repository in New Mexico. This project is an integral part of the SRP Long Range TRU Waste Management Program to reduce the amount of TRU waste stored at SRP. The TWF is designed to process 15,000 cubic feet of retrieved waste and 6200 cubic feet of newly generated waste each year of operation. This facility is designed to minimize direct personnel contact with the waste using state-of-the-art remotely operated equipment

Fiber optic pressure sensors for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hashemian, H.M.; Black, C.L. [Analysis and Measurement Services Corp., Knoxville, TN (United States)

1995-04-01

In the last few years, the nuclear industry has experienced some problems with the performance of pressure transmitters and has been interested in new sensors based on new technologies. Fiber optic pressure sensors offer the potential to improve on or overcome some of the limitations of existing pressure sensors. Up to now, research has been motivated towards development and refinement of fiber optic sensing technology. In most applications, reliability studies and failure mode analyses remain to be exhaustively conducted. Fiber optic sensors have currently penetrated certain cutting edge markets where they possess necessary inherent advantages over other existing technologies. In these markets (e.g. biomedical, aerospace, automotive, and petrochemical), fiber optic sensors are able to perform measurements for which no alternate sensor previously existed. Fiber optic sensing technology has not yet been fully adopted into the mainstream sensing market. This may be due to not only the current premium price of fiber optic sensors, but also the lack of characterization of their possible performance disadvantages. In other words, in conservative industries, the known disadvantages of conventional sensors are sometimes preferable to unknown or not fully characterized (but potentially fewer and less critical) disadvantages of fiber optic sensors. A six-month feasibility study has been initiated under the auspices of the US Nuclear Regulatory Commission (NRC) to assess the performance and reliability of existing fiber optic pressure sensors for use in nuclear power plants. This assessment will include establishment of the state of the art in fiber optic pressure sensing, characterization of the reliability of fiber optic pressure sensors, and determination of the strengths and limitations of these sensors for nuclear safety-related services.

Fiber optic pressure sensors for nuclear power plants

International Nuclear Information System (INIS)

Hashemian, H.M.; Black, C.L.

1995-01-01

In the last few years, the nuclear industry has experienced some problems with the performance of pressure transmitters and has been interested in new sensors based on new technologies. Fiber optic pressure sensors offer the potential to improve on or overcome some of the limitations of existing pressure sensors. Up to now, research has been motivated towards development and refinement of fiber optic sensing technology. In most applications, reliability studies and failure mode analyses remain to be exhaustively conducted. Fiber optic sensors have currently penetrated certain cutting edge markets where they possess necessary inherent advantages over other existing technologies. In these markets (e.g. biomedical, aerospace, automotive, and petrochemical), fiber optic sensors are able to perform measurements for which no alternate sensor previously existed. Fiber optic sensing technology has not yet been fully adopted into the mainstream sensing market. This may be due to not only the current premium price of fiber optic sensors, but also the lack of characterization of their possible performance disadvantages. In other words, in conservative industries, the known disadvantages of conventional sensors are sometimes preferable to unknown or not fully characterized (but potentially fewer and less critical) disadvantages of fiber optic sensors. A six-month feasibility study has been initiated under the auspices of the US Nuclear Regulatory Commission (NRC) to assess the performance and reliability of existing fiber optic pressure sensors for use in nuclear power plants. This assessment will include establishment of the state of the art in fiber optic pressure sensing, characterization of the reliability of fiber optic pressure sensors, and determination of the strengths and limitations of these sensors for nuclear safety-related services

Preparation and characterization of corn reinforced polymer sheet of fibers

International Nuclear Information System (INIS)

Moreira, Tatiana Martinez; Seo, Emilia Satoshi Miyamaru

2016-01-01

There is a global trend in seeking plant fibers to replace the synthetic fibers to obtain reinforced composites aimed at the use of renewable resources. In this context, this paper aims to develop the process of preparing maize leaf fibers, characterizing them and adapting them for applications in the construction industry and develop a reinforced polymer composite with these fibers. Corn leaves were dried in environmental temperature, treated by mercerizing, then neutralized with acid solution and washed in running water. The characterization of the corn leaf fibers was carried out by X-ray diffraction, X-ray fluorescence, scanning electron microscopy, specific surface area, thermogravimetry and specific mass. The mercerizing treatment was effective, because the maize fibers have characteristics similar to synthetic fibers, leading to a possibility of new technological uses. The polymeric composite material was developed by extrusion processes and injection and tested for tensile testing, differential scanning calorimetry and scanning electron microscopy, thus reused an organic waste that would be disposed of by inserting it in a technological process, contributing to the research and development of new polymeric materials as well as to reduce waste discarded as scrap. (author)

Solid municipal waste processing plants: Cost benefit analysis

International Nuclear Information System (INIS)

Gerardi, V.

1992-01-01

This paper performs cost benefit analyses on three solid municipal waste processing alternatives with plants of diverse daily outputs. The different processing schemes include: selected wastes incineration with the production of refuse derived fuels; selected wastes incineration with the production of refuse derived fuels and compost; pyrolysis with energy recovery in the form of electric power. The plant daily outputs range from 100 to 300 tonnes for the refuse derived fuel alternatives, and from 200 to 800 tonnes for the pyrolysis/power generation scheme. The cost analyses consider investment periods of fifteen years in duration and interest rates of 5%

Waste generation comparison: Coal-fired versus nuclear power plants

International Nuclear Information System (INIS)

LaGuardia, T.S.

1998-01-01

Low-level radioactive waste generation and disposal attract a great deal of attention whenever the nuclear industry is scrutinized by concerned parties, be it the media, the public, or political interests. It is therefore important to the nuclear industry that this issue be put into perspective relative to other current forms of energy production. Most of the country's fossil-fueled power comes from coal-fired plants, with oil and gas as other fuel sources. Most of the generated waste also comes from coal plants. This paper, therefore, compares waste quantities generated by a typical (1150-MW(electric)) pressurized water reactor (PWR) to that of a comparably sized coal-fired power plant

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

Region 9 NPDES Facilities - Waste Water Treatment Plants

Science.gov (United States)

Point geospatial dataset representing locations of NPDES Waste Water Treatment Plant Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates direct discharges from facilities that discharge treated waste water into waters of the US. Facilities are issued NPDES permits regulating their discharge as required by the Clean Water Act. A facility may have one or more outfalls (dischargers). The location represents the facility or operating plant.

Radioactive waste treatment technology at Czech nuclear power plants

International Nuclear Information System (INIS)

Kulovany, J.

2001-01-01

This presentation describes the main technologies for the treatment and conditioning of radioactive wastes at Czech nuclear power plants. The main technologies are bituminisation for liquid radioactive wastes and supercompaction for solid radioactive wastes. (author)

Increasing operational efficiency in a radioactive waste processing plant - 16100

International Nuclear Information System (INIS)

Turner, T.W.; Watson, S.N.

2009-01-01

The solid waste plant at Harwell in Oxfordshire, contains a purpose built facility to input, assay, visually inspect and sort remote handled intermediate level radioactive waste (RHILW). The facility includes a suite of remote handling cells, known as the head-end cells (HEC), which waste must pass through in order to be repackaged. Some newly created waste from decommissioning works on site passes through the cells, but the vast majority of waste for processing is historical waste, stored in below ground tube stores. Existing containers are not suitable for long term storage, many are already badly corroded, so the waste must be efficiently processed and repackaged in order to achieve passive safety. The Harwell site is currently being decommissioned and the land is being restored. The site is being progressively de-licensed, and redeveloped as a business park, which can only be completed when all the nuclear liabilities have been removed. The recovery and processing of old waste in the solid waste plant is a key project linked to de-licensing of a section of the site. Increasing the operational efficiency of the waste processing plant could shorten the time needed to clear the site and has the potential to save money for the Nuclear Decommissioning Authority (NDA). The waste processing facility was constructed in the mid 1990's, and commissioned in 1999. Since operations began, the yearly throughput of the cells has increased significantly every year. To achieve targets set out in the lifetime plan (LTP) for the site, throughput must continue to increase. The operations department has measured the overall equipment effectiveness (OEE) of the process for the last few years, and has used continuous improvement techniques to decrease the average cycle time. Philosophies from operational management practices such as 'lean' and 'kaizen' have been employed successfully to drive out losses and increase plant efficiency. This paper will describe how the solid waste plant

Radioactive wastes from reprocessing plants

International Nuclear Information System (INIS)

Huppert, K.L.

1977-01-01

The lecture deals with definition, quantity and type of radioactive waste products occurring in a fuel reprocessing plant. Solid, liquid and gaseous fission and activation products are formed during the dissolution of the fuel and during the extraction process, and they must be separated from the fissionalble uranium and plutonium not spent. The chemical behaviour of these products (Zr, Ru, Np, gaseous substances, radiolysis products), which is sometimes very problematic, necessitates careful process control. However, the lifetime of nuclides is just as important for the conditions of the reprocessing procedure. The types of waste obtained after reprocessing are classified according to their state of aggregation and level of activity and - on the basis of the operational data of a prototype plant - they are quantitatively extrapolated for the operation of a large-scale facility of 1,400 tons of fuel annually. (RB) [de

Development of bitumization plant of radioactive waste

International Nuclear Information System (INIS)

Lee, S.H.; Chun, K.S.; Song, H.Y.; Park, S.H.; Park, W.J.; Ryoo, R.; Cho, W.J.; Wee, K.S.; Lee, J.D.

1981-01-01

This study is to develop the bitumization techniques of radioactive waste concentrates from nuclear power plants (PWR), Cold-run and hot-run bitumization pilot plant were designed and constructed, and testing was carried out. The results show that the range of pH 7 to 8, in which a soluble product could form, is suitable for feeding in the waste and for its incorporation into asphalt, domestic blown asphalt is suitable up to an exposure of 10 8 rad. The estimated viscosity of the asphalt/waste product is about 14 poises at 175 0 C and the asphalt/wastes products in simulated sea-water for three weeks showed no evidence of swelling. The leaching rate from the spent resin/asphalt products in distilled water less than 1/1000 of that from the cement-products. It is considered that the resin content which is suitable for the incorporation of spent resin into asphalt is less than 50 wt%

Component design considerations for gas turbine HTGR waste-heat power plant

International Nuclear Information System (INIS)

McDonald, C.F.; Vrable, D.L.

1976-01-01

Component design considerations are described for the ammonia waste-heat power conversion system of a large helium gas-turbine nuclear power plant under development by General Atomic Company. Initial component design work was done for a reference plant with a 3000-MW(t) High-Temperature Gas-Cooled Reactor (HTGR), and this is discussed. Advanced designs now being evaluated include higher core outlet temperature, higher peak system pressures, improved loop configurations, and twin 4000-MW(t) reactor units. Presented are the design considerations of the major components (turbine, condenser, heat input exchanger, and pump) for a supercritical ammonia Rankine waste heat power plant. The combined cycle (nuclear gas turbine and waste-heated plant) has a projected net plant efficiency of over 50 percent. While specifically directed towards a nuclear closed-cycle helium gas-turbine power plant (GT-HTGR), it is postulated that the bottoming waste-heat cycle component design considerations presented could apply to other low-grade-temperature power conversion systems such as geothermal plants

Waste Isolation Pilot Plant No-migration variance petition

International Nuclear Information System (INIS)

1990-03-01

This report describes various aspects of the Waste Isolation Pilot Plant (WIPP) including design data, waste characterization, dissolution features, ground water hydrology, natural resources, monitoring, general geology, and the gas generation/test program

Processing constraints on high-level nuclear waste glasses for Hanford Waste Vitrification Plant

International Nuclear Information System (INIS)

Hrma, P.R.

1993-09-01

The work presented in this paper is a part of a major technology program supported by the U.S. Department of Energy (DOE) in preparation for the planned operation of the Hanford Waste Vitrification Plant (HWVP). Because composition of Hanford waste varies greatly, processability is a major concern for successful vitrification. This paper briefly surveys general aspects of waste glass processability and then discusses their ramifications for specific examples of Hanford waste streams

Waste Isolation Pilot Plant Safety Analysis Report. Volume 5

International Nuclear Information System (INIS)

1986-01-01

This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

Waste Isolation Pilot Plant Safety Analysis Report. Volume 4

International Nuclear Information System (INIS)

1986-01-01

This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

Waste Isolation Pilot Plant Safety Analysis Report. Volume 1

International Nuclear Information System (INIS)

1986-01-01

This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection: Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating control and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

Waste Isolation Pilot Plant Safety Analysis Report. Volume 2

International Nuclear Information System (INIS)

1986-01-01

This Safety Analysis Report (SAR) has been prepared by the US Department of Energy (DOE) to support the construction and operation of the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP facility is designed to receive, inspect, emplace, and store unclassified defense-generated transuranic wastes in a retrievable fashion in an underground salt medium and to conduct studies and perform experiments in salt with high-level wastes. Upon the successful completion of these studies and experiments, WIPP is designed to serve as a permanent facility. The first chapter of this report provides a summary of the location and major design features of WIPP. Chapters 2 through 5 describe the site characteristics, design criteria, and design bases used in the design of the plant and the plant operations. Chapter 6 discusses radiation protection; Chapters 7 and 8 present an accident analysis of the plant and an assessment of the long-term waste isolation at WIPP. The conduct of operations and operating controls and limits are discussed in Chapters 9 and 10. The quality assurance programs are described in Chapter 11

Retrieval of canistered experimental waste at the waste isolation pilot plant

International Nuclear Information System (INIS)

Stinebaugh, R.E.

1979-07-01

To assess the suitability of bedded salt for nuclear waste disposal, an extensive experimental program will be implemented at the Waste Isolation Pilot Plant. In order to evaluate experimental results, it will be necessary to recover certain of these experiments for postmortem examination and analysis. This document describes the equipment and procedures used to effect recovery of one category of WIPP experiments

Low-level radioactive waste associated with plant life extension

International Nuclear Information System (INIS)

Sciacca, F.; Zigler, G.; Walsh, R.

1992-01-01

Many utilities operating nuclear power plants are expected to seek to extend the useful life of their plants through license renewal. These US Nuclear Regulatory Commission (NRC) licensees are expected to implement enhanced inspection, surveillance, testing, and monitoring (ISTM) as needed to detect and mitigate age-related degradation of important structures, systems, and components (SSCs). In addition, utilities may undertake various refurbishment and upgrade activities at these plants to better assure economic and reliable power generation. These activities performed for safety and/or economic reasons can result in radioactive waste generation, which is incremental to that generated in the original licensing term. Work was performed for the NRC to help define and characterize potential environmental impacts associated with nuclear plant license renewal and plant life extension. As part of this work, projections were made of the types and quantities of low-level radioactive waste (LLRW) likely to be generated by licensee programs. These projections were needed to estimate environmental impacts related to the disposal of such wastes

STORAGE AND RECOVERY OF SECONDARY WASTE COMING FROM MUNICIPAL WASTE INCINERATION PLANTS IN UNDERGROUND MINE

Directory of Open Access Journals (Sweden)

Waldemar Korzeniowski

2016-09-01

Full Text Available Regarding current and planned development of municipal waste incineration plants in Poland there is an important problem of the generated secondary waste management. The experience of West European countries in mining shows that waste can be stored successfully in the underground mines, but especially in salt mines. In Poland there is a possibility to set up the underground storage facility in the Salt Mine “Kłodawa”. The mine today is capable to locate over 3 million cubic meters and in the future it can increase significantly. Two techniques are proposed: 1 – storage of packaged waste, 2 – waste recovery as selfsolidifying paste with mining technology for rooms backfilling. Assuming the processing capacity of the storage facility as 100 000 Mg of waste per year, “Kłodawa” mine will be able to accept around 25 % of currently generated waste coming from the municipal waste incineration plants and the current volume of the storage space is sufficient for more than 20 years. Underground storage and waste recovery in mining techniques are beneficial for the economy and environment.

Waste acceptance criteria for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1996-04-01

The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies

Analysis of a bio-electrochemical reactor containing carbon fiber textiles for the anaerobic digestion of tomato plant residues.

Science.gov (United States)

Hirano, Shin-Ichi; Matsumoto, Norio

2018-02-01

A bio-electrochemical system packed with supporting material can promote anaerobic digestion for several types of organic waste. To expand the target organic matters of a BES, tomato plant residues (TPRs), generated year-round as agricultural and cellulosic waste, were treated using three methanogenic reactors: a continuous stirred tank reactor (CSTR), a carbon fiber textile (CFT) reactor, and a bio-electrochemical reactor (BER) including CFT with electrochemical regulation (BER + CFT). CFT had positive effects on methane fermentation and methanogen abundance. The microbial population stimulated by electrochemical regulation, including hydrogenotrophic methanogens, cellulose-degrading bacteria, and acetate-degrading bacteria, suppressed acetate accumulation, as evidenced by the low acetate concentration in the suspended fraction in the BER + CFT. These results indicated that the microbial community in the BER + CFT facilitated the efficient decomposition of TPR and its intermediates such as acetate to methane. Copyright © 2017 Elsevier Ltd. All rights reserved.

Management of low level wastes at Rokkasho reprocessing plant

International Nuclear Information System (INIS)

Moriya, N.; Ochi, E.

2006-01-01

Full text: At Rokkasho Reprocessing Plant (RRP), after start-up of the commercial operation, radioactive wastes will be generated. Wastes generated from a reprocessing plant generally consist of many kinds of characteristics in view of ''activity level'', ''nuclide composition'', ''chemical properties'', ''physical properties'', and so on. For stable operation of a reprocessing plant, we should t reat , ''condition'' and ''dispose'' these wastes considering these wastes characteristics. To contribute to the nuclear fuel cycle project, it is important to evaluate technologies such as, ''Treatment'', ''Conditioning'' and ''Final Disposal'', not only for technical but also for economical aspects. Considering the final disposal in the future, the basic policy in ''Treatment'' and ''Conditioning'' at RRP is shown below: Recover and reuse chemicals (such as nitric acid and TBP, etc.) in plant; Radioactive waste shall be divided, classified and managed according to activity level, nuclide composition, the radiation level, its physical properties, chemical properties, etc.; Treat them based on ''classification'' management with proper combination; Condition them as intermediate forms in order to keep flexibility in the future disposal method; Original volume of annually generated wastes at RRP is estimated as 5600m3 except highly radioactive vitrified waste, and these wastes shall be treated in the following units, which are now under commisioning, in order to reduce and stabilize wastes. Low-level concentrated liquid waste to be treated with a ''Drying and peptization'' unit; Spent solvent to be treated with a ''Pyrolysis and hydrothermal solidification'' unit; Relatively low-level non-alfa flammable wastes to be treated with a ''Incineration and hydrothermal solidification'' unit; CB/BP (Channel Box and Burnable Poison) to be processed with a ''Cutting'' unit; Other wastes to be kept as their generated state with a ''Intermediate storage''. As a result of these

Hanford Waste Vitrification Plant quality assurance program description for defense high-level waste form development and qualification

International Nuclear Information System (INIS)

Hand, R.L.

1990-12-01

The US Department of Energy-Office of Civilian Radioactive Waste Management has been designated the national high-level waste repository licensee and the recipient for the canistered waste forms. The Office of Waste Operations executes overall responsibility for producing the canistered waste form. The Hanford Waste Vitrification Plant Project, as part of the waste form producer organization, consists of a vertical relationship. Overall control is provided by the US Department of Energy-Environmental Restoration and Waste Management Headquarters; with the US Department of Energy-Office of Waste Operations; the US Department of Energy- Headquarters/Vitrification Project Branch; the US Department of Energy-Richland Operations Office/Vitrification Project Office; and the Westinghouse Hanford Company, operations and engineering contractor. This document has been prepared in response to direction from the US Department of Energy-Office of Civilian Radioactive Waste Management through the US Department of Energy-Richland Operations Office for a quality assurance program that meets the requirements of the US Department of Energy. This document provides guidance and direction for implementing a quality assurance program that applies to the Hanford Waste Vitrification Plant Project. The Hanford Waste Vitrification Plant Project management commits to implementing the quality assurance program activities; reviewing the program periodically, and revising it as necessary to keep it current and effective. 12 refs., 6 figs., 1 tab

The Stored Waste Examination Pilot Plant program at the INEL

International Nuclear Information System (INIS)

McKinley, K.B.; Anderson, B.C.; Clements, T.L.; Hinckley, J.P.; Mayberry, J.L.; Smith, T.H.

1983-01-01

Since 1970, defense transuranic waste has been placed into 20-year retrievable storage at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory (INEL). A major objective of the U.S. Department of Energy (DOE) Nuclear Waste Management Program is to remove all retrievably stored transuranic waste from the INEL. The January 1981 DOE Record of Decision on the Waste Isolation Pilot Plant (WIPP) stated, ''The WIPP facility will dispose of defense transuranic waste stored retrievably at the Idaho National Engineering Laboratory.'' After retrieval and before shipment, processing may be necessary to prepare the waste for acceptance, handling, and enhanced long-term isolation in the WIPP. However, some of the waste is certifiable to the WIPP waste acceptance criteria without container opening or waste processing. To minimize costs, the Stored Waste Examination Pilot Plant (SWEPP) is being developed to certify INEL stored transuranic waste without container opening or waste processing. The SWEPP certification concept is based on records assessment, nondestructive examination techniques, assay techniques, health physics examinations, and limited opening of containers at another facility for quality control

Polymer solidification of mixed wastes at the Rocky Flats Plant

International Nuclear Information System (INIS)

Faucette, A.M.; Logsdon, B.W.; Lucerna, J.J.; Yudnich, R.J.

1994-01-01

The Rocky Flats Plant is pursuing polymer solidification as a viable treatment option for several mixed waste streams that are subject to land disposal restrictions within the Resource Conservation and Recovery Act provisions. Tests completed to date using both surrogate and actual wastes indicate that polyethylene microencapsulation is a viable treatment option for several mixed wastes at the Rocky Flats Plant, including nitrate salts, sludges, and secondary wastes such as ash. Treatability studies conducted on actual salt waste demonstrated that the process is capable of producing waste forms that comply with all applicable regulatory criteria, including the Toxicity Characteristic Leaching Procedure. Tests have also been conducted to evaluate the feasibility of macroencapsulating certain debris wastes in polymers. Several methods and plastics have been tested for macroencapsulation, including post-consumer recycle and regrind polyethylene

Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report

Energy Technology Data Exchange (ETDEWEB)

Britt, Phillip F [ORNL

2015-03-01

Analysis of Waste Isolation Pilot Plant Samples: Integrated Summary Report. Summaries of conclusions, analytical processes, and analytical results. Analysis of samples taken from the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico in support of the WIPP Technical Assessment Team (TAT) activities to determine to the extent feasible the mechanisms and chemical reactions that may have resulted in the breach of at least one waste drum and release of waste material in WIPP Panel 7 Room 7 on February 14, 2014. This report integrates and summarizes the results contained in three separate reports, described below, and draws conclusions based on those results. Chemical and Radiochemical Analyses of WIPP Samples R-15 C5 SWB and R16 C-4 Lip; PNNL-24003, Pacific Northwest National Laboratory, December 2014 Analysis of Waste Isolation Pilot Plant (WIPP) Underground and MgO Samples by the Savannah River National Laboratory (SRNL); SRNL-STI-2014-00617; Savannah River National Laboratory, December 2014 Report for WIPP UG Sample #3, R15C5 (9/3/14); LLNL-TR-667015; Lawrence Livermore National Laboratory, January 2015 This report is also contained in the Waste Isolation Pilot Plant Technical Assessment Team Report; SRNL-RP-2015-01198; Savannah River National Laboratory, March 17, 2015, as Appendix C: Analysis Integrated Summary Report.

Uptake by plants of radionuclides from FUSRAP waste materials

International Nuclear Information System (INIS)

Knight, M.J.

1983-04-01

Radionuclides from FUSRAP wastes potentially may be taken up by plants during remedial action activities and permanent near-surface burial of contaminated materials. In order to better understand the propensity of radionuclides to accumulate in plant tissue, soil and plant factors influencing the uptake and accumulation of radionuclides by plants are reviewed. In addition, data describing the uptake of the principal radionuclides present in FUSRAP wastes (uranium-238, thorium-230, radium-226, lead-210, and polonium-210) are summarized. All five radionuclides can accumulate in plant root tissue to some extent, and there is potential for the translocation and accumulation of these radionuclides in plant shoot tissue. Of these five radionuclides, radium-226 appears to have the greatest potential for translocation and accumulation in plant shoot tissue. 28 references, 1 figure, 3 tables

Uptake by plants of radionuclides from FUSRAP waste materials

Energy Technology Data Exchange (ETDEWEB)

Knight, M.J.

1983-04-01

Radionuclides from FUSRAP wastes potentially may be taken up by plants during remedial action activities and permanent near-surface burial of contaminated materials. In order to better understand the propensity of radionuclides to accumulate in plant tissue, soil and plant factors influencing the uptake and accumulation of radionuclides by plants are reviewed. In addition, data describing the uptake of the principal radionuclides present in FUSRAP wastes (uranium-238, thorium-230, radium-226, lead-210, and polonium-210) are summarized. All five radionuclides can accumulate in plant root tissue to some extent, and there is potential for the translocation and accumulation of these radionuclides in plant shoot tissue. Of these five radionuclides, radium-226 appears to have the greatest potential for translocation and accumulation in plant shoot tissue. 28 references, 1 figure, 3 tables.

B Plant complex hazardous, mixed and low level waste certification plan

International Nuclear Information System (INIS)

Beam, T.G.

1994-11-01

This plan describes the administrative steps and handling methodology for certification of hazardous waste, mixed waste, and low level waste generated at B Plant Complex. The plan also provides the applicable elements of waste reduction and pollution prevention, including up front minimization and end product reduction of volume and/or toxicity. The plan is written to satisfy requirements for Hanford Site waste generators to have a waste certification program in place at their facility. This plan, as described, applies only to waste which is generated at, or is the responsibility of, B Plant Complex. The scope of this plan is derived from the requirements found in WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria

B Plant complex hazardous, mixed and low level waste certification plan

Energy Technology Data Exchange (ETDEWEB)

Beam, T.G.

1994-11-01

This plan describes the administrative steps and handling methodology for certification of hazardous waste, mixed waste, and low level waste generated at B Plant Complex. The plan also provides the applicable elements of waste reduction and pollution prevention, including up front minimization and end product reduction of volume and/or toxicity. The plan is written to satisfy requirements for Hanford Site waste generators to have a waste certification program in place at their facility. This plan, as described, applies only to waste which is generated at, or is the responsibility of, B Plant Complex. The scope of this plan is derived from the requirements found in WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria.

Industrial Qualification Process for Optical Fibers Distributed Strain and Temperature Sensing in Nuclear Waste Repositories

Directory of Open Access Journals (Sweden)

S. Delepine-Lesoille

2012-01-01

Full Text Available Temperature and strain monitoring will be implemented in the envisioned French geological repository for high- and intermediate-level long-lived nuclear wastes. Raman and Brillouin scatterings in optical fibers are efficient industrial methods to provide distributed temperature and strain measurements. Gamma radiation and hydrogen release from nuclear wastes can however affect the measurements. An industrial qualification process is successfully proposed and implemented. Induced measurement uncertainties and their physical origins are quantified. The optical fiber composition influence is assessed. Based on radiation-hard fibers and carbon-primary coatings, we showed that the proposed system can provide accurate temperature and strain measurements up to 0.5 MGy and 100% hydrogen concentration in the atmosphere, over 200 m distance range. The selected system was successfully implemented in the Andra underground laboratory, in one-to-one scale mockup of future cells, into concrete liners. We demonstrated the efficiency of simultaneous Raman and Brillouin scattering measurements to provide both strain and temperature distributed measurements. We showed that 1.3 μm working wavelength is in favor of hazardous environment monitoring.

Q Fever Outbreak among Workers at a Waste-Sorting Plant.

Directory of Open Access Journals (Sweden)

Eva Alonso

Full Text Available An outbreak of Q fever occurred in February-April 2014 among workers at a waste-sorting plant in Bilbao (Spain. The outbreak affected 58.5% of investigated employees, 47.2% as confirmed cases (PCR and/or serology and 11.3% as probable cases (symptoms without laboratory confirmation. Only employees who had no-access to the waste processing areas of the plant were not affected and incidence of infection was significantly higher among workers not using respiratory protection masks. Detection by qPCR of Coxiella burnetii in dust collected from surfaces of the plant facilities confirmed exposure of workers inside the plant. Animal remains sporadically detected among the residues received for waste-sorting were the most probable source of infection. After cleaning and disinfection, all environmental samples tested negative. Personal protection measures were reinforced and made compulsory for the staff and actions were taken to raise farmers' awareness of the biological risk of discharging animal carcasses as urban waste.

Survey of minipower plant for municipal solid waste firing

International Nuclear Information System (INIS)

Merkkiniemi, R.; Hyoety, P.; Saiha, E.

1999-01-01

Dumping of municipal waste to disposal areas has caused environmental problems, and this has led to more sophisticated disposal systems and high prices. That and a general demand to reduce the quantity of waste require new solutions, and a question has been arisen whether combustion could be used to treat waste. This project is concentrating to bum waste in a small-scale power plant. The background is one 10-MW pilot in Tampere city based on smelting furnace and a 0.3-MW pyrolyse furnace. The results of these from the viewpoint of operation and effluent were satisfactory and the burning process used is in line with the latest regulations. The second aspect is the economy of waste handling. The minipower plant is designed for reasonable small municipalities, abt 20 000 inhabitants or 1 - 20 MW heat input. According to several feasibility studies this method is the cheapest way to handle waste. A local heat demand is used to support the economy. The prices of products, heat and power, and cost are of the same level as the market prices. Thus, we expect a economical and environmentally safe operation with the minipower plant and it will also give a hint to solve a higher capacity demand of one unit. (orig.)

Hanford Waste Vitrification Plant capacity increase options

International Nuclear Information System (INIS)

Larson, D.E.

1996-04-01

Studies are being conducted by the Hanford Waste Vitrification Plant (HWVP) Project on ways to increase the waste processing capacity within the current Vitrification Building structural design. The Phase 1 study on remote systems concepts identification and extent of capacity increase was completed. The study concluded that the HWVP capacity could be increased to four times the current capacity with minor design adjustments to the fixed facility design, and the required design changes would not impact the current footprint of the vitrification building. A further increase in production capacity may be achievable but would require some technology development, verification testing, and a more systematic and extensive engineering evaluation. The primary changes included a single advance melter with a higher capacity, new evaporative feed tank, offgas quench collection tank, ejector venturi scrubbers, and additional inner canister closure station,a smear test station, a new close- coupled analytical facility, waste hold capacity of 400,000 gallon, the ability to concentrate out-of-plant HWVP feed to 90 g/L waste oxide concentration, and limited changes to the current base slab construction package

Resource conservation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

1993-08-01

Volume I contains the following attachments for Module II: waste analysis plan; quality assurance program plan for the Waste Isolation Pilot Plant (WIPP) Experiment Waste Characterization Program(QAPP); WIPP Characterization Sampling and Analysis Guidance Manual (Plan)(SAP); and no migration Determination Requirement Summary (NMD)

Conceptual project of waste treatment plant of CDTN

International Nuclear Information System (INIS)

Gabriel, J.L.; Astolfi, D.

1983-01-01

This paper presents the conceptual project of the waste treatment plant of CDTN. Several areas, such as: process area, material entrance and exit area are studied. The treatment processes are: evaporation, filtration, cementation, cutting and processing of solid wastes. (C.M.)

Standards development for fiber optic spectroscopic components for adverse environments

Science.gov (United States)

Saggese, Steven J.; Greenwell, Roger A.

1994-09-01

Optical fiber sensors are finding wider use in all types of applications involving adverse environments, including exposure to radiation. In order to effectively characterize and evaluate the performance of a fiber sensor system for a radiation environment, such as within a nuclear power plant or in a radioactive waste storage/disposal facility, it is beneficial to develop standard test procedures. Science & Engineering Associates (SEA) has developed two such procedures for the American Society for Testing and Materials (ASTM) which address the testing of optical fibers for remote Raman spectroscopic and broadband sensor applications in a steady state radiation environment.

Radioactive Bench-scale Steam Reformer Demonstration of a Monolithic Steam Reformed Mineralized Waste Form for Hanford Waste Treatment Plant Secondary Waste - 12306

Energy Technology Data Exchange (ETDEWEB)

Evans, Brent; Olson, Arlin; Mason, J. Bradley; Ryan, Kevin [THOR Treatment Technologies, LLC - 106 Newberry St. SW, Aiken, SC 29801 (United States); Jantzen, Carol; Crawford, Charles [Savannah River Nuclear Solutions (SRNL), LLC, Aiken, SC 29808 (United States)

2012-07-01

Hanford currently has 212,000 m{sup 3} (56 million gallons) of highly radioactive mixed waste stored in the Hanford tank farm. This waste will be processed to produce both high-level and low-level activity fractions, both of which are to be vitrified. Supplemental treatment options have been under evaluation for treating portions of the low-activity waste, as well as the liquid secondary waste from the low-activity waste vitrification process. One technology under consideration has been the THOR{sup R} fluidized bed steam reforming process offered by THOR Treatment Technologies, LLC (TTT). As a follow-on effort to TTT's 2008 pilot plant FBSR non-radioactive demonstration for treating low-activity waste and waste treatment plant secondary waste, TTT, in conjunction with Savannah River National Laboratory, has completed a bench scale evaluation of this same technology on a chemically adjusted radioactive surrogate of Hanford's waste treatment plant secondary waste stream. This test generated a granular product that was subsequently formed into monoliths, using a geo-polymer as the binding agent, that were subjected to compressibility testing, the Product Consistency Test and other leachability tests, and chemical composition analyses. This testing has demonstrated that the mineralized waste form, produced by co-processing waste with kaolin clay using the TTT process, is as durable as low-activity waste glass. Testing has shown the resulting monolith waste form is durable, leach resistant, and chemically stable, and has the added benefit of capturing and retaining the majority of Tc-99, I-129, and other target species at high levels. (authors)

A review of potential uses for fiber optic sensors in nuclear power plants, with attendant benefits in plant safety and operational efficiency

International Nuclear Information System (INIS)

Holcomb, D.E.; Antonescu, C.

1994-01-01

Fiber optic-based sensing has a wide range of potential applications in nuclear power plants, and a fiber optic analog presently exists for virtually every conventional nuclear power plant sensing system. Fiber optic-based sensors are likely to eventually supplant many conventional sensors because of their inherent advantages-reduced mass, reduced size, ruggedness to vibration and shock, physical flexibility, high sensitivity, electrical isolation, extreme resistance to electromagnetic interference, high temperature resistance, reduced calibration requirements, passive operation, and high radiation resistance. In addition, fiber optic-based sensors exist which are capable of measuring parameters important to safety and performance which cannot be conventionally measured (high electromagnetic field, in-core, and distributed measurements). However, fiber optic sensors remain at too low a level of development for immediate application in safety-critical systems. Moreover, fiber optic sensors have different failure modes and mechanisms than conventional sensors; hence, considerable regulatory research will be necessary to establish the technical basis for the use of fiber optic sensors in safety-critical systems

Waste retrieval plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1993-03-01

The US DOE has prepared this plan to meet the requirements of Public Law 102579, the Waste Isolation Pilot Plant (WIPP) LWA, The purpose. is to demonstrate readiness to retrieve from the WIPP underground transuranic radioactive waste that will be used for testing should retrieval be needed. The WIPP, a potential geologic repository for transuranic wastes generated in national-defense activities, has been constructed in southeastern New Mexico. Because the transuranic wastes will remain radioactive for a very long time, the WIPP must reasonably ensure safe performance over thousands of years. The DOE therefore decided to develop the facility in phases, to preclude premature decisions and to conduct the performance assessments needed to demonstrate long-term safety. Surface facilities for receiving waste have been built, and considerable underground excavation, 2150 feet below the surface, has been completed. The next step is a test phase, including underground experiments called ''bin tests'' and ''alcove test(s)'' with contact-handled transuranic waste. The objective of these waste tests is to collect relevant data about the gas-generation potential and volatile organic compound (VOC) source term of the waste for developing a basis for demonstrating long term safety by compliance with the applicable disposal regulations (40 CFR 191, 264 and 268). The test phase will end when a decision is made to begin disposal in the WIPP or to terminate the project if regulatory compliance cannot be determined and demonstrated. Authorization to receive transuranic waste at the WIPP for the test phase is given by the WIPP LWA provided certain requirements are met

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

Hanford Waste Vitrification Plant Clean Air Act permit application

International Nuclear Information System (INIS)

1990-04-01

This document briefly describes the Hanford Site and provides a general overview of the Hanford Waste Vitrification Plant (HWVP). Other topics include sources of emissions, facility operating parameters, facility emissions, pollutant and radionuclide control technology and air quality. The HWVP will convert mixed wastes (high-activity radioactive and hazardous liquid wastes) to a solid vitrified form (borosilicate glass) for disposal. Mixed wastes pretreated in the Hanford Site B Plant will be pumped into double- shell tanks in the 200 East Area for interim storage. This pretreated mixed waste will be batch transferred from interim storage to the HWVP facility, where the waste will be concentrated by evaporation, treated with chemicals, and mixed with glass-forming materials. The mixture will then be continuously fed into an electrically heated glass melter. The molten glass will be poured into canisters that will be cooled, sealed, decontaminated, and stored until the vitrified product can be transferred to a geologic repository. 25 refs., 18 figs., 32 tabs

Region 9 NPDES Facilities 2012- Waste Water Treatment Plants

Science.gov (United States)

Point geospatial dataset representing locations of NPDES Waste Water Treatment Plant Facilities. NPDES (National Pollution Discharge Elimination System) is an EPA permit program that regulates direct discharges from facilities that discharge treated waste water into waters of the US. Facilities are issued NPDES permits regulating their discharge as required by the Clean Water Act. A facility may have one or more outfalls (dischargers). The location represents the facility or operating plant.

Rock mechanics activities at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Francke, C.; Saeb, S.

1996-01-01

The application of rock mechanics at nuclear waste repositories is a true multidisciplinary effort. A description and historical summary of the Waste Isolation Pilot Plant (WIPP) is presented. Rock mechanics programs at the WIPP are outlined, and the current rock mechanics modeling philosophy of the Westinghouse Waste Isolation Division is discussed

A new semi-mobile plant for radiation processing of waste

International Nuclear Information System (INIS)

Iacoboni, V.; Liccione, G.; Schwarz, M.; Tata, A.; Fantini, M.

1998-01-01

A new pilot/demonstrative semi-mobile irradiation plant, named TRIRIS (TRIsaia-RIfiuti-Sterilizzazione, namely ''Trisaia Res. Center - Wastes - Sterilization''), has been designed and erected in order to propose and explore new technological opportunities, based on in ''in-situ'' effective cleaning process. The main general goal is to face increased problems and concerns related to the treatment/disposal of different solid-liquid wastes, particularly with reference to emergency situation (e.g. need of quick environment restoring operation following an accident with groundwater pollution). The project, which was jointly carried out by ENEA and Hitesys Co., an Italian electron accelerators manufacturer, foresees a LINAC type EB-machine (s band) having 4-6 MeV and till 1000 W as beam features. A highly flexible automatic system allows materials (solid or liquid wastes) transporting and handling to be equipped with a belt conveyor and a piping net. Scattered radiation shielding is performed by a water pool surrounding the EB-machine head, filled up before operations. Auxiliary systems, control console and analytical chemical laboratories are hosted in suitable containers near the plant and are easily transportable. The whole plant and annexed systems disassembling and reassembling in a new site can be easily carried out in a short time (few days). The plant, located at ENEA-Trisaia Res. Center (Basilicata, southern Italy), allows a large operative flexibility: groundwater and wastewater decontamination (1800 to 70 kg/h in the 1 to 25 kGy dose range), organic and chlorinated waste streams (25 kg/h at 75 kGy), solid hospital wastes (50 kg/h at 35 kGy) or hazardous wastes like polycyclic aromatic compounds (180 to 35 kg/h in the 10 to 50 kGy dose range). The paper describes and illustrates the plant in details and presents the first available operating results so far performed by the installed plant

Radioactive waste disposal: Waste isolation pilot plants (WIPP). (Latest citations from the NTIS Bibliographic database). Published Search

International Nuclear Information System (INIS)

1993-09-01

The bibliography contains citations concerning the Waste Isolation Pilot Plant (WIPP), a geologic repository located in New Mexico for transuranic wastes generated by the U.S. Government. Articles follow the development of the program from initial site selection and characterization through construction and testing, and examine research programs on environmental impacts, structural design, and radionuclide landfill gases. Existing plants and facilities, pilot plants, migration, rock mechanics, economics, regulations, and transport of wastes to the site are also included. The Salt Repository Project and the Crystalline Repository Project are referenced in separate bibliographies. (Contains a minimum of 228 citations and includes a subject term index and title list.)

Containers of Attalea funifera fibers to produce eucalyptus seedlings

Directory of Open Access Journals (Sweden)

Andrea Vita Reis Mendonça

2016-09-01

Full Text Available The aim of this study was to assess the technical feasibility of using biodegradable containers made of fiber waste of Attalea funifera Martius to produce seedling of Eucalyptus camaldulensis Dehnh. The work was carried out in three stages: manufacture of piassava fiber containers, seedling production and field simulation. The experiment of seedling production was in completely randomized design, with two treatments (polyethylene tube and biodegradable container and 10 repetitions, with 64 seedlings per repetition. After 93 days, seedlings were evaluated based on quality variables. The simuation of initial growth of seedlings in the field consisted in planting seedlings in containers of 11L, in completely randomized design, with three treatments: seedlings produced in polyethylene tubes; seedlings produced in biodegradable containers, without removal of the container during planting; and seedlings produced in biodegradable containers, with removal of the container at planting, with ten repetitions, with one seedling by repetition. The biodegradable container withstood the production cycle and resulted in seedlings within acceptable standards quality. The use of biodegradable container, made of palm fibers, waived the removal of this vessel in the final planting.

CFD modeling and experience of waste-to-energy plant burning waste wood

DEFF Research Database (Denmark)

Rajh, B.; Yin, Chungen; Samec, N.

2013-01-01

Computational Fluid Dynamics (CFD) is being increasingly used in industry for in-depth understanding of the fundamental mixing, combustion, heat transfer and pollutant formation in combustion processes and for design and optimization of Waste-to-Energy (WtE) plants. In this paper, CFD modeling...... the conversion of the waste wood in the fuel bed on the grate, which provides the appropriate inlet boundary condition for the freeboard 3D CFD simulation. The CFD analysis reveals the detailed mixing and combustion characteristics in the waste wood-fired furnace, pinpointing how to improve the design...

Waste Isolation Pilot Plant RH TRU waste preoperational checkout: Final report

International Nuclear Information System (INIS)

1988-06-01

This report documents the results of the Waste Isolation Pilot Plant (WIPP) Remote-Handled Transuranic (RH TRU) Waste Preoperational Checkout. The primary objective of this checkout was to demonstrate the process of handling RH TRU waste packages, from receipt through emplacement underground, using equipment, personnel, procedures, and methods to be used with actual waste packages. A further objective was to measure operational time lines to provide bases for confirming the WIPP design through put capability and for projecting operator radiation doses. Successful completion of this checkout is a prerequisite to the receipt of actual RH TRU waste. This checkout was witnessed in part by members of the Environmental Evaluation Group (EEG) of the state of New Mexico. Further, this report satisfies a key milestone contained in the Agreement for Consultation and Cooperation with the state of New Mexico. 4 refs., 26 figs., 4 tabs

Hanford Waste Vitrification Plant Technology Plan

International Nuclear Information System (INIS)

Sexton, R.A.

1988-06-01

The reference Hanford plan for disposal of defense high-level waste is based on waste immobilization in glass by the vitrification process and temporary vitrified waste storage at the Hanford Site until final disposal in a geologic repository. A companion document to the Hanford Waste Management Plan (HWMP) is the Draft, Interim Hanford Waste Management Technology Plan (HWMTP), which provides a description of the technology that must be developed to meet the reference waste management plan. One of the issues in the HWMTP is DST-6, Immobilization (Glass). The HWMTP includes all expense funding needed to complete the Hanford Waste Vitrification Plant (HWVP) project. A preliminary HWVP Technology Plan was prepared in 1985 as a supporting document to the HWMTP to provide a more detailed description of the technology needed to construct and operate a vitrification facility. The plan was updated and issued in 1986, and revised in 1987. This document is an annual update of the plan. The HWVP Technology Plan is limited in scope to technology that requires development or confirmation testing. Other expense-funded activities are not included. The relationship between the HWVP Technology Plan and other waste management issues addressed in the HWMTP is described in section 1.6 of this plan. 6 refs., 4 figs., 34 tabs

Management of radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

Krause, H.

1984-01-01

The importance of radioactive wastes from nuclear power plants (NPPs) results primarily from their large amounts. In NPPs more radioactive wastes arise than in all other plants of the nuclear fuel cycle, with the exception of uranium mills. Although the volume is great, NPP wastes are relatively low in activity and radiotoxicity and short in half-life. Several methods for treatment of NPP wastes are available that meet all the relevant requirements and they have attained high technical standards and are highly reliable. Consequently, the discharge of radionuclides with liquid and gaseous effluents and the resulting dose commitment to the general public are far below established limits. The quality of the conditioned wastes conforms to the requirements for ultimate disposal. The final disposal of NPP wastes has already been demonstrated successfully in several places and the feasibility of NPP decommissioning and management of the wastes arising in this process have been proved. The problems associated with the management of radioactive wastes from NPPs have been solved both scientifically and technically; there is no urgent need for improvement. This is why for new developments cost-benefit aspects must be considered, including the dose commitment to the operating staff and general aspects such as public acceptance and socio-ethical questions. Spectacular new developments are not to be expected in the near future. However, by continuous improvement of details and optimization of the whole system useful contributions can still be made to develop nuclear technology further. (author)

Critique of Hanford Waste Vitrification Plant off-gas sampling requirements

International Nuclear Information System (INIS)

Goles, R.W.

1996-03-01

Off-gas sampling and monitoring activities needed to support operations safety, process control, waste form qualification, and environmental protection requirements of the Hanford Waste Vitrification Plant (HWVP) have been evaluated. The locations of necessary sampling sites have been identified on the basis of plant requirements, and the applicability of Defense Waste Processing Facility (DWPF) reference sampling equipment to these HWVP requirements has been assessed for all sampling sites. Equipment deficiencies, if present, have been described and the bases for modifications and/or alternative approaches have been developed

Description of a ceramic waste form and canister for Savannah River Plant high-level waste

International Nuclear Information System (INIS)

Butler, J.L.; Allender, J.S.; Gould, T.H. Jr.

1982-04-01

A canistered ceramic waste form for possible immobilization of Savannah River Plant (SRP) high-level radioactive wastes is described. Characteristics reported for the form include waste loading, chemical composition, heat content, isotope inventory, mechanical and thermal properties, and leach rates. A conceptual design of a potential production process for making this canistered form are also described. The ceramic form was selected in November 1981 as the primary alternative to the reference waste form, borosilicate glass, for making a final waste form decision for SRP waste by FY-1983. 11 tables

Denitration of Savannah River Plant waste streams

International Nuclear Information System (INIS)

Orebaugh, E.G.

1976-07-01

Partial denitration of waste streams from Savannah River Plant separations processes was shown to significantly reduce the quantity of waste solids to be stored as an alkaline salt cake. The chemical processes involved in the denitration of nonradioactive simulated waste solutions were studied. Chemical and instrumental analytical techniques were used to define both the equilibrium concentrations and the variation of reactants and products in the denitration reaction. Mechanisms were proposed that account for the complicated chemical reactions observed in the simulated waste solutions. Metal nitrates can be denitrated by reaction with formic acid only by the release of nitric acid from hydrolysis or formate complexation of metal cations. However, eventual radiolysis of formate salts or complexes results in the formation of biocarbonate and makes complexation-denitration a nonproductive means of reducing waste solids. Nevertheless, destruction of nitrate associated with free acid and easily hydrolyzable cations such as iron, mercury, and zirconium can result in greater than 30 percent reduction in waste solids from five SRP waste streams

Management of nontritium radioactive wastes from fusion power plants

International Nuclear Information System (INIS)

Kaser, J.D.; Postma, A.K.; Bradley, D.J.

1976-09-01

This report identifies nontritium radioactive waste sources for current conceptual fusion reactor designs. Quantities and compositions of the radwaste are estimated for the tokamaks of the University of Wisconsin (UWMAK-I), the Princeton Plasma Physics Laboratory (PPPL), and the Oak Ridge National Laboratory (ORNL); the Reference Theta Pinch Reactor of the Los Alamos Scientific Laboratory (LASL); and the Minimum Activation Blanket of the Brookhaven National Laboratory (BNL). Disposal of large amounts of radioactive waste appears necessary for fusion reactors. Although the curie (Ci) level of the wastes is comparable to that of fission products in fission reactors, the isotopes are less hazardous, and have shorter half-lives. Therefore radioactivity from fusion power production should pose a smaller risk than radioactivity from fission reactors. Radioactive waste sources identified for the five reference plants are summarized. Specific radwaste treatments or systems had to be assumed to estimate these waste quantities. Future fusion power plant conceptual designs should include radwaste treatment system designs so that assumed designs do not have to be used to assess the environmental effects of the radioactive waste

Waste Isolation Pilot Plant Safety Analysis Report

International Nuclear Information System (INIS)

1995-11-01

The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions'' (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.'' This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment

Waste Isolation Pilot Plant Safety Analysis Report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-11-01

The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

Geopolymerisation of silt generated from construction and demolition waste washing plants.

Science.gov (United States)

Lampris, C; Lupo, R; Cheeseman, C R

2009-01-01

Recycling plants that size, sort and wash construction and demolition waste can produce high quality aggregate. However, they also produce up to 80ton per hour of filter cake waste containing fine (waste and normally landfilled. This research investigated the potential to form geopolymers containing silt, which would allow this problematic waste to be beneficially reused as aggregate. This would significantly improve the economic viability of recycling plants that wash wastes. Silt filter cakes have been collected from a number of aggregate washing plants operating in the UK. These were found to contain similar aluminosilicate crystalline phases. Geopolymer samples were produced using silt and silt mixed with either metakaolin or pulverised fuel ash (PFA). Silt geopolymers cured at room temperature had average 7-day compressive strengths of 18.7MPa, while partial substitution of silt by metakaolin or PFA increased average compressive strengths to 30.5 and 21.9MPa, respectively. Curing specimens for 24h at 105 degrees C resulted in a compressive strength of 39.7MPa and microstructural analysis confirmed the formation of dense materials. These strengths are in excess of those required for materials to be used as aggregate, particularly in unbound applications. The implications of this research for the management of waste silt at construction and demolition waste washing plants are discussed.

The Potential in Bioethanol Production From Waste Fiber Sludges in Pulp Mill-Based Biorefineries

Science.gov (United States)

Sjöde, Anders; Alriksson, Björn; Jönsson, Leif J.; Nilvebrant, Nils-Olof

Industrial production of bioethanol from fibers that are unusable for pulp production in pulp mills offers an approach to product diversification and more efficient exploitation of the raw material. In an attempt to utilize fibers flowing to the biological waste treatment, selected fiber sludges from three different pulp mills were collected, chemically analyzed, enzymatically hydrolyzed, and fermented for bioethanol production. Another aim was to produce solid residues with higher heat values than those of the original fiber sludges to gain a better fuel for combustion. The glucan content ranged between 32 and 66% of the dry matter. The lignin content varied considerably (1-25%), as did the content of wood extractives (0.2-5.8%). Hydrolysates obtained using enzymatic hydrolysis were found to be readily fermentable using Saccharomyces cerevisiae. Hydrolysis resulted in improved heat values compared with corresponding untreated fiber sludges. Oligomeric xylan fragments in the solid residue obtained after enzymatic hydrolysis were identified using matrix-assisted laser desorption ionization-time of flight and their potential as a new product of a pulp mill-based biorefinery is discussed.

Characterization of Savannah River Plant waste glass

International Nuclear Information System (INIS)

Plodinec, M.J.

1985-01-01

The objective of the glass characterization programs at the Savannah River Laboratory (SRL) is to ensure that glass containing Savannah River Plant high-level waste can be permanently stored in a federal repository, in an environmentally acceptable manner. To accomplish this objective, SRL is carrying out several experimental programs, including: fundamental studies of the reactions between waste glass and water, particularly repository groundwater; experiments in which candidate repository environments are simulated as accurately as possible; burial tests of simulated waste glass in candidate repository geologies; large-scale tests of glass durability; and determination of the effects of process conditions on glass quality. In this paper, the strategy and current status of each of these programs is discussed. The results indicate that waste packages containing SRP waste glass will satisfy emerging regulatory criteria

Combating corrosion in biomass and waste fired plant

Energy Technology Data Exchange (ETDEWEB)

Henderson, Pamela [Vattenfall AB, Stockholm (Sweden). Research and Development; Hjoernhede, Anders [Vattenfall AB, Gothenburg (Sweden). Power Consultant

2010-07-01

Many biomass- or waste-fired plants have problems with high temperature corrosion especially if the steam temperature is greater than 500 C. An increase in the combustion of waste fuels means that an increasing number of boilers have had problems. Therefore, there is great interest in reducing the costs associated with high temperature corrosion and at the same time there exists a desire to improve the electrical efficiency of a plant by the use of higher steam temperatures. Assuming that the fuel is well-mixed and that there is good combustion control, there are in addition a number of other measures which can be used to reduce superheater corrosion in biomass and waste fired plants, and these are described in this paper. These include the use of fuel additives, specifically sulphur-containing ones; design aspects like placing superheaters in less corrosive positions in a boiler, using tube shielding, a wider pitch between the tubes; operational considerations such as more controlled soot-blowing and the use of better materials. (orig.)

[Mercury Distribution Characteristics and Atmospheric Mercury Emission Factors of Typical Waste Incineration Plants in Chongqing].

Science.gov (United States)

Duan, Zhen-ya; Su, Hai-tao; Wang, Feng-yang; Zhang, Lei; Wang, Shu-xiao; Yu, Bin

2016-02-15

Waste incineration is one of the important atmospheric mercury emission sources. The aim of this article is to explore the atmospheric mercury pollution level of waste incineration industry from Chongqing. This study investigated the mercury emissions from a municipal solid waste incineration plant and a medical waste incineration plant in Chongqing. The exhaust gas samples in these two incineration plants were obtained using USA EPA 30B method. The mercury concentrations in the fly ash and bottom ash samples were analyzed. The results indicated that the mercury concentrations of the municipal solid waste and medical waste incineration plant in Chongqing were (26.4 +/- 22.7) microg x m(-3) and (3.1 +/- 0.8) microg x m(-3) in exhaust gas respectively, (5279.2 +/- 798.0) microg x kg(-1) and (11,709.5 +/- 460.5) microg x kg(-1) in fly ash respectively. Besides, the distribution proportions of the mercury content from municipal solid waste and medical waste in exhaust gas, fly ash, and bottom ash were 34.0%, 65.3%, 0.7% and 32.3%, 67.5%, 0.2% respectively; The mercury removal efficiencies of municipal solid waste and medical waste incineration plants were 66.0% and 67.7% respectively. The atmospheric mercury emission factors of municipal solid waste and medical waste incineration plants were (126.7 +/- 109.0) microg x kg(-1) and (46.5 +/- 12.0) microg x kg(-1) respectively. Compared with domestic municipal solid waste incineration plants in the Pearl River Delta region, the atmospheric mercury emission factor of municipal solid waste incineration plant in Chongqing was lower.

Deriving a Planting Medium from Solid Waste Compost and Construction, Demolition and Excavation Waste

Science.gov (United States)

Farajalla, Nadim; Assaf, Eleni; Bashour, Issam; Talhouk, Salma

2014-05-01

Lebanon's very high population density has been increasing since the end of the war in the early 1990s reaching 416.36 people per square kilometer. Furthermore, the influx of refugees from conflicts in the region has increased the resident population significantly. All these are exerting pressure on the country's natural resources, pushing the Lebanese to convert more forest and agricultural land into roads, buildings and houses. This has led to a building boom and rapid urbanization which in turn has created a demand for construction material - mainly rock, gravel, sand, etc. nearly all of which were locally acquired through quarrying to the tune of three million cubic meters annually. This boom has been followed by a war with Israel in 2006 which resulted in thousands of tonnes of debris. The increase in population has also led to an increase in solid waste generation with 1.57 million tonnes of solid waste generated in Lebanon per year. The combination of construction, demolition and excavation (CDE) waste along with the increase in solid waste generation has put a major stress on the country and on the management of its solid waste problem. Compounding this problem are the issues of quarries closure and rehabilitation and a decrease in forest and vegetative cover. The on-going research reported in this paper aims to provide an integrated solution to the stated problem by developing a "soil mix" derived from a mélange of the organic matter of the solid waste (compost), the CDE waste, and soil. In this mix, native and indicator plants are planted (in pots) from which the most productive mix will be selected for further testing at field level in later experiments. The plant species used are Matiolla, a native Lebanese plant and Zea mays, which is commonly known used as an indicator plant due to its sensitivity to environmental conditions. To ensure sustainability and environmental friendliness of the mix, its physical and chemical characteristics are monitored

Criteria impacting shipments of Rocky Flats Plant radioactive mixed wastes

International Nuclear Information System (INIS)

Clawson, R.L.; Eide, J.H.

1992-05-01

Westinghouse Hanford Company, Transportation and Packaging Division, under contract for the Los Alamos Technology Office-Rocky Flats Plant, has developed this synopsis report to be used as a reference in the development of the Rocky Flats Plant Comprehensive Treatment and Management Plan and the Rocky Flats Plant Residue Elimination Plan. This report represents the criteria for packaging, shipping, and transporting Rocky Flats Plant radioactive mixed wastes. It is a compilation of state and federal regulations, US Department of Energy orders, and acceptance criteria specific to US Department of Energy radioactive mixed waste treatment, storage and disposal facilities

Hazard caused by radioactive wastes from nuclear power plants in comparison with both natural hazards and those caused by solid wastes from coal-fired plants

International Nuclear Information System (INIS)

Strupczewski, A.

1988-01-01

The risks concerned with radioactive solid wastes deposited deeply underground as well as with low-, intermediate- and high-level radioactive wastes are compared with natural radioactivity and thermal plants solid wastes threats. 17 refs., 5 figs., 4 tabs. (A.S.)

Radioactive wastes management in fiscal year 1983 in the fuel reprocessing plant

International Nuclear Information System (INIS)

1985-01-01

In the nuclear fuel reprocessing plant of Power Reactor and Nuclear Fuel Development Corporation, the releases of radioactive gaseous and liquid wastes are so managed not to exceed the respective objective release levels. Of the radioactive liquid wastes, the high level concentrated wastes are stored in tanks and the low level wastes are stored in tanks or asphalt solidified. For radioactive solid wastes, high level solid wastes are stored in casks, low level solid wastes and asphalt solids in drums etc. The releases of radioactive gaseous and liquid wastes in the fiscal year 1983 were below the objective release levels. The radioactive wastes management in the fuel reprocessing plant in fiscal year 1983 is given in tables, the released quantities, the stored quantities, etc. (Mori, K.)

Management of radioactive wastes at nuclear power plants

International Nuclear Information System (INIS)

2008-03-01

This Regulation refers to the requirements of the Regulation CNEN-NE.1.26, 'Safety Operation of Nuclear Power Plants', as expressed in the section 13, specifically in the subsection 13.4, relatives to the management of radioactive wastes at nuclear power plants

Disposal of slightly contaminated radioactive wastes from nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Minns, J.L. [Nuclear Regulatory Commission, Washington, DC (United States)

1995-02-01

With regard to the disposal of solid wastes, nuclear power plants basically have two options, disposal in a Part 61 licensed low-level waste site, or receive approval pursuant to 20.2002 for disposal in a manner not otherwise authorized by the NRC. Since 1981, the staff has reviewed and approved 30 requests for disposal of slightly contaminated radioactive materials pursuant to Section 20.2002 (formerly 20.302) for nuclear power plants located in non-Agreement States. NRC Agreement States have been delegated the authority for reviewing and approving such disposals (whether onsite or offsite) for nuclear power plants within their borders. This paper describes the characteristics of the waste disposed of, the review process, and the staff`s guidelines.

Overview of Savannah River Plant waste management operations

International Nuclear Information System (INIS)

Haywood, J.E.; Killian, T.H.

1987-01-01

The Du Pont Savannah River Plant (SRP) Waste Management Program is committed to the safe handling, storage, and disposal of wastes that result from the production of special nuclear materials for the US Department of Energy (US DOE). High-level radioactive liquid waste is stored in underground carbon steel tanks with double containment, and the volume is reduced by evaporation. An effluent treatment facility is being constructed to treat low-level liquid hazardous and radioactive waste. Solid low-level waste operations have been improved through the use of engineered low-level trenches, and transuranic waste handling procedures were modified in 1974 to meet new DOE criteria requiring 20-year retrievable storage. An improved disposal technique, Greater Confinement Disposal, is being demonstrated for intermediate-level waste. Nonradioactive hazardous waste is stored on site in RCRA interim status storage buildings. 5 figs

Radioactive waste management at nuclear power plant Cernavoda

International Nuclear Information System (INIS)

Raducea, D.

2002-01-01

Many human activities generate waste, but people are worried about wastes produced in nuclear power plants (NPPs). Their concern is an unjustified fear toward the hazards from radioactive waste, probably because in any country generating electric power by NPPs a lot of attention is paid to relevant parties involved in radioactive waste management. Significant attention is also given to the management of radioactive waste at the Cemavoda NPP. The general approach required for the collection, handling, conditioning and storage of radioactive wastes, while maintaining acceptable levels of safety for workers, members of the public and the environment, is conceptually established. The overall programme provides the necessary facilities to adequately manage solid radioactive waste from Cemavoda NPP Unit 1 and will be capable of expansion when other units are brought into service. (author)

Startup and operation of a plant-scale continuous glass melter for vitrification of Savannah River Plant simulated waste

International Nuclear Information System (INIS)

Willis, T.A.

1980-01-01

The reference process for disposal of radioactive waste from the Savannah River Plant is vitrification of the waste in borosilicate glass in a continuous glass melter. Design, startup, and operation of a plant-scale developmental melter system are discussed

Test phase plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1993-03-01

The US Department of Energy (DOE) has prepared this Test Phase Plan for the Waste Isolation Pilot Plant to satisfy the requirements of Public Law 102-579, the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act (LWA). The Act provides seven months after its enactment for the DOE to submit this Plan to the Environmental Protection Agency (EPA) for review. A potential geologic repository for transuranic wastes, including transuranic mixed wastes, generated in national-defense activities, the WIPP is being constructed in southeastern New Mexico. Because these wastes remain radioactive and chemically hazardous for a very long time, the WIPP must provide safe disposal for thousands of years. The DOE is developing the facility in phases. Surface facilities for receiving waste have been built and considerable underground excavations (2150 feet below the surface) that are appropriate for in-situ testing, have been completed. Additional excavations will be completed when they are required for waste disposal. The next step is to conduct a test phase. The purpose of the test phase is to develop pertinent information and assess whether the disposal of transuranic waste and transuranic mixed waste in the planned WIPP repository can be conducted in compliance with the environmental standards for disposal and with the Solid Waste Disposal Act (SWDA) (as amended by RCRA, 42 USC. 6901 et. seq.). The test phase includes laboratory experiments and underground tests using contact-handled transuranic waste. Waste-related tests at WIPP will be limited to contact-handled transuranic and simulated wastes since the LWA prohibits the transport to or emplacement of remote-handled transuranic waste at WIPP during the test phase

Optimal control of a waste water cleaning plant

Directory of Open Access Journals (Sweden)

Ellina V. Grigorieva

2010-09-01

Full Text Available In this work, a model of a waste water treatment plant is investigated. The model is described by a nonlinear system of two differential equations with one bounded control. An optimal control problem of minimizing concentration of the polluted water at the terminal time T is stated and solved analytically with the use of the Pontryagin Maximum Principle. Dependence of the optimal solution on the initial conditions is established. Computer simulations of a model of an industrial waste water treatment plant show the advantage of using our optimal strategy. Possible applications are discussed.

Enviromental impact of a hospital waste incineration plant in Krakow (Poland).

Science.gov (United States)

Gielar, Agnieszka; Helios-Rybicka, Edeltrauda

2013-07-01

The environmental impact of a hospital waste incineration plant in Krakow was investigated. The objective of this study was to assess the degree of environmental effect of the secondary solid waste generated during the incineration process of medical waste. The analysis of pollution of the air emissions and leaching test of ashes and slag were carried out. The obtained results allowed us to conclude that (i) the hospital waste incineration plant significantly solves the problems of medical waste treatment in Krakow; (ii) the detected contaminant concentrations were generally lower than the permissible values; (iii) the generated ashes and slag contained considerable concentrations of heavy metals, mainly zinc, and chloride and sulfate anions. Ashes and slag constituted 10-15% of the mass of incinerated wastes; they are more harmful for the environment when compared with untreated waste, and after solidification they can be deposited in the hazardous waste disposal.

The Waste Treatment Plant, a Work in Progress

International Nuclear Information System (INIS)

Hamel, W. F. Jr.; Duncan, G. M.

2006-01-01

There are many challenges in the design and construction of Department of Energy's (DOE) Waste Treatment and Immobilization Plant (WTP) at the Hanford site. The plant is being built to process some 55 million gallons of radioactive waste from 177 underground tanks. Engineering and construction are progressing on this largest project in the DOE complex. This paper describes some of WTP's principal recent challenges and opportunities and how they are being addressed to minimize impact on the project, enhance the capabilities of the facilities, and reduce risk. A significant new development in 2005 was the need to account for higher seismic accelerations than originally specified for the facility structures and equipment. Efforts have centered on continuing design and construction with minimal risk, while the final seismic design spectra was developed. Other challenges include development of an alternative cesium ion exchange resin to minimize the risk from reliance on a single product, implementing advanced analytical techniques to improve laboratory performance, adopting a thinner walled high level waste (HLW) canister to reduce waste volume and mission duration, and commissioning a comprehensive external flowsheet review of the design, along with its underpinning technologies, and projected plant operability. These challenges make it clear that WTP is a work in progress, but the challenges are being successfully resolved as the design and construction move on to completion. (authors)

Waste-to-energy advanced cycles and new design concepts for efficient power plants

CERN Document Server

Branchini, Lisa

2015-01-01

This book provides an overview of state-of-the-art technologies for energy conversion from waste, as well as a much-needed guide to new and advanced strategies to increase Waste-to-Energy (WTE) plant efficiency. Beginning with an overview of municipal solid waste production and disposal, basic concepts related to Waste-To-Energy conversion processes are described, highlighting the most relevant aspects impacting the thermodynamic efficiency of WTE power plants. The pervasive influences of main steam cycle parameters and plant configurations on WTE efficiency are detailed and quantified. Advanc

Radioactive liquid waste processing system

International Nuclear Information System (INIS)

Inakuma, Masahiko; Takahara, Nobuaki; Hara, Satomi.

1996-01-01

Laundry liquid wastes and shower drains containing radioactive materials generated in a nuclear power plant are removed with radioactive materials by a fiber filtration device and an activated carbon filtration device to satisfy standers of water quality described in the environmental effect investigation report. Spent activated carbon is dehydrated together with the back-wash liquid from the fiber filtration device and the activated carbon filtration device using a Nutsche-type filtration dryer. With such procedures, the scale of the facility is minimized, space for devices, maintenance for equipments and radiation dose rate are reduced. (T.M.)

The Savannah River Plant low-level waste segregation program

International Nuclear Information System (INIS)

Wheeler, V.B.

1987-01-01

To extend the life of the Savannah River Plant (SRP) Radioactive Waste Burial Ground, a sitewide program has been implemented to segregate waste that is essentially free of contamination from routine radioactive waste. Much of the low-level waste disposed of as radioactive has no detectable contamination and can be buried in a sanitary landfill. A Landfill Monitoring Facility (LMF) will be constructed at SRP to house the state-of-the-art technology required to provide a final survey on the candidate waste streams that had previously been classified as radioactive. 3 figs

Liquid waste management at nuclear power plant with WWER

International Nuclear Information System (INIS)

Sabouni, Zahra.

1995-07-01

Management of radioactive wastes have become an area of ever increasing important in nuclear power plants. This is due to the fact that national and international regulations will only allow activity release to the environment based on ALARA principles. Radioactive liquids in the nuclear power plant originate as leakage from equipment, as drains from reactor and auxiliary systems, from decontamination and cleaning operations, from active laundry and from personnel showers. They will collected through the controlled zone of the plant in sumps and automatically pumped to large tanks and then to treatment system. The radioactive wastes are separated and categorized according to their main physical and chemical properties. Methods most frequently applied for low and intermediate level; liquid wastes are: chemical treatment (precipitation), ion exchange, and evaporation, and the decontamination ors are a few hundred, 10 2 -10 4 and 10 3 -10 6 , respectively. As a result of the treatment of radioactive liquids by mentioned methods a concentration of activity takes place in filter media, ion exchange resins, and evaporator concentrates. Before the semi-solid wastes shipped for storage, it has to be solidified in order to handle and transport in easier way. The solidification of wastes can take place by different methods. The general methods are: cementation, and bituminization processes. The selection of each process will depend on many factors which should be considered during the design phase. (author)

Performance Using Bamboo Fiber Ash Concrete as Admixture Adding Superplasticizer

Science.gov (United States)

Vasudevan, Gunalaan

2017-06-01

The increasing demand on natural resources for housing provisions in developing countries have called for sourcing and use of sustainable local materials for building and housing delivery. Natural materials to be considered sustainable for building construction should be ‘green’ and obtained from local sources, including rapidly renewable plant materials like palm fronds and bamboo, recycled materials and other products that are reusable and renewable. Each year, tens of millions of tons of bamboo are utilized commercially, generating a vast amount of waste. Besides that, bamboo fiber is easy availability, low density, low production cost and satisfactory mechanical properties. One solution is to activate this waste by using it as an additive admixture in concrete to keep it out of landfills and save money on waste disposal. The research investigates the mechanical and physical properties of bamboo fiber powder in a blended Portland cement. The structural value of the bamboo fiber powder in a blended Portland cement was evaluated with consideration for its suitability in concrete. Varied percentage of bamboo fiber powder (BFP) at 0%, 5%, 10%, 15%, and 20% as an admixture in 1:2:4 concrete mixes. The workability of the mix was determined through slump; standard consistency test was carried on the cement. Compressive strength of hardened cured (150 x 150 x 150) mm concrete cubes at 7days, 14days and 28days were tested.

Design of Radioactive Waste Management Systems at Nuclear Power Plants

International Nuclear Information System (INIS)

1986-01-01

This Safety Guide is addressed to the administrative and technical authorities and specialists dealing with the design, construction and operation of nuclear power plants, and in particular waste management facilities at nuclear power plants. This Guide has been prepared as part of the IAEA Waste Handling, Treatment and Storage programme. It is a follow-up document to the Code of Practice on Management of Radioactive Wastes from Nuclear Power Plants published in 1985 in the IAEA Safety Standards, Safety Series No. 69, in which basic principles for management of radioactive wastes at nuclear power plants are set out. The IAEA has established wide ranging programmes to provide Member States with guidance on different aspects of safety and technology related to thermal neutron power reactors and associated nuclear fuel cycle operations, including those for management of radioactive wastes. There are many IAEA publications related to various technical and safety aspects of different nuclear energy applications. All these publications are issued by the Agency for the use of Member States in connection with their own nuclear technological safety requirements. They are based on national experience contributed by experts from different countries and relate to common features in approaches to the problems discussed. However, the final decision and legal responsibility in any regulatory procedure always rest with the Member State. This particular Guide aims to provide general and detailed principles for the design of waste management facilities at nuclear power plants. It emphasizes what and how specific safety requirements for the management of radioactive wastes from nuclear power plants can be met in the design and construction stage. The safety requirements for operation of such facilities will be considered in the Agency's next Safety Series publication, Safety Guide 50-SG-011, Operational Management for Radioactive Effluents and Wastes Arising in Nuclear Power Plants

Hazardous waste management plan, Savannah River Plant

International Nuclear Information System (INIS)

Phifer, M.A.

1984-06-01

All SRP waste storage, disposal, and recycling facilities that have received hazardous waste, low-level radioactive hazardous waste (mixed waste) or process waste since 1980 have been evaluated by EPA standards. Generally the waste storage areas meet all applicable standards. However, additional storage facilities currently estimated at $2 million and waste disposal facilities currently estimated at $20 million will be required for proper management of stored waste. The majority of the disposal facilities are unlined earthen basins that receive hazardous or process wastes and have or have the potential to contaminate groundwater. To come into compliance with the groundwater standards the influents to the basins will be treated or discontinued, the basins will be decommissioned, groundwater monitoring will be conducted, and remedial actions will be taken as necessary. The costs associated with these basin actions are not completely defined and will increase from present estimates. A major cost which has not been resolved is associated with the disposal of the sludge produced from the treatment plants and basin decommissioning. The Low-Level Radioactive Burial Ground which is also a disposal facility has received mixed waste; however, it does not meet the standards for hazardous waste landfills. In order to properly handle mixed wastes additional storage facilities currently estimated at $500,000 will be provided and options for permanent disposal will be investigated

B Plant Complex generator dangerous waste storage areas inspection plan: Revision 1

International Nuclear Information System (INIS)

Beam, T.G.

1994-01-01

This document contains the inspection plan for the <90 day dangerous/mixed waste storage areas and satellite accumulation areas at B Plant Complex. This inspection plan is designed to comply with all applicable federal, state and US Department of Energy-Richland Operations Office training requirements. In particular, the requirements of WAC 173-303 ''Dangerous Waste Regulations'' are met by this inspection plan. This inspection plan is designed to provide B Plant Complex with the records and documentation showing that the waste storage and handling program is in compliance with applicable regulations. The plan also includes the requirements for becoming a qualified inspector of waste storage areas and the responsibilities of various individuals and groups at B Plant Complex

Trim waste minimization at the Pinellas Plant

International Nuclear Information System (INIS)

DeLaneuville, D.

1992-01-01

Bacteria counts and several methods of slowing bacterial growth in machine trim coolant are suggested to reduce the frequency of coolant replacement without risking employee health or the longevity of the product or machinery. On-site treatment and disposal of waste trim are recommended to further reduce waste volume. This paper discusses the benefits of these efforts, including projected cost savings based on partial implementation at the Department of Energy's Pinellas Plant

Plutonium Finishing Plant (PFP) Treatment and Storage Unit Waste Analysis Plan

International Nuclear Information System (INIS)

PRIGNANO, A.L.

2000-01-01

The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Plutonium Finishing Plant Treatment and Storage Unit (PFP Treatment and Storage Unit) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (4)(a) and (5). The PFP Treatment and Storage Unit is an interim status container management unit for plutonium bearing mixed waste radiologically managed as transuranic (TRU) waste. TRU mixed (TRUM) waste managed at the PFP Treatment and Storage Unit is destined for the Waste Isolation Pilot Plant (WIPP) and therefore is not subject to land disposal restrictions [WAC 173-303-140 and 40 CFR 268]. The PFP Treatment and Storage Unit is located in the 200 West Area of the Hanford Facility, Richland Washington (Figure 1). Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

Revised concept for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Dennis, A.W.; Milloy, J.A.; Scully, L.W.; Shefelbine, H.C.; Stinebaugh, R.E.; Wowak, W.E.

1978-07-01

The quantities of remotely handled wastes that must be handled at the Waste Isolation Pilot Plant have been reduced from 250 x 10 3 ft 3 /y to 10 x 10 3 ft 3 /y; the capital cost of the facility will be reduced from 534 to 428 million dollars. Changes in the facility design due to the reduction in the amount of remote-handled waste are discussed. If DOE should exercise its option to construct a high-level waste repository concurrently with the construction of the revised design, with both facilities receiving waste in 1985, the combined cost would be about 580 million dollars. However, it is unlikely that significant quantities of high-level waste in a form suitable for geologic disposal would be available until after 1990. (13 figures, 5 tables)

Waste Treatment Plant - 12508

Energy Technology Data Exchange (ETDEWEB)

Harp, Benton; Olds, Erik [US DOE (United States)

2012-07-01

The Waste Treatment Plant (WTP) will immobilize millions of gallons of Hanford's tank waste into solid glass using a proven technology called vitrification. The vitrification process will turn the waste into a stable glass form that is safe for long-term storage. Our discussion of the WTP will include a description of the ongoing design and construction of this large, complex, first-of-a-kind project. The concept for the operation of the WTP is to separate high-level and low-activity waste fractions, and immobilize those fractions in glass using vitrification. The WTP includes four major nuclear facilities and various support facilities. Waste from the Tank Farms is first pumped to the Pretreatment Facility at the WTP through an underground pipe-in-pipe system. When construction is complete, the Pretreatment Facility will be 12 stories high, 540 feet long and 215 feet wide, making it the largest of the four major nuclear facilities that compose the WTP. The total size of this facility will be more than 490,000 square feet. More than 8.2 million craft hours are required to construct this facility. Currently, the Pretreatment Facility is 51 percent complete. At the Pretreatment Facility the waste is pumped to the interior waste feed receipt vessels. Each of these four vessels is 55-feet tall and has a 375,000 gallon capacity, which makes them the largest vessels inside the Pretreatment Facility. These vessels contain a series of internal pulse-jet mixers to keep incoming waste properly mixed. The vessels are inside the black-cell areas, completely enclosed behind thick steel-laced, high strength concrete walls. The black cells are designed to be maintenance free with no moving parts. Once hot operations commence the black-cell area will be inaccessible. Surrounded by black cells, is the 'hot cell canyon'. The hot cell contains all the moving and replaceable components to remove solids and extract liquids. In this area, there is ultrafiltration

Pretreatment of Hanford purex plant first-cycle waste

International Nuclear Information System (INIS)

Gibson, M.W.; Gerboth, D.M.; Peters, B.B.

1987-01-01

A process has been developed to pretreat neutralized, first-cycle high-level waste from the fuels reprocessing facility (PUREX Plant) at the Hanford Site. The process separates solids from the supernate liquid, which contains soluble salts. The solids, including most of the fission products and transuranic elements, may then be vitrified for disposal, while the low-level supernate stream may be processed into a less expensive grout waste form. The process also includes ion exchange treatment of the separated supernate stream to remove radiocesium. A flow sheet based on these operations was completed to support a planned demonstration of the process in the Hanford site B Plant canyon facility

Cellulosic Fibers: Effect of Processing on Fiber Bundle Strength

DEFF Research Database (Denmark)

Thygesen, Anders; Madsen, Bo; Thomsen, Anne Belinda

2011-01-01

A range of differently processed cellulosic fibers from flax and hemp plants were investigated to study the relation between processing of cellulosic fibers and fiber bundle strength. The studied processing methods are applied for yarn production and include retting, scutching, carding, and cotto......A range of differently processed cellulosic fibers from flax and hemp plants were investigated to study the relation between processing of cellulosic fibers and fiber bundle strength. The studied processing methods are applied for yarn production and include retting, scutching, carding...

Waste Isolation Pilot Plant 1999 Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Evans, Roy B.; Adams, Amy; Martin, Don; Morris, Randall C.; Reynolds, Timothy D.; Warren, Ronald W.

2000-09-30

The U.S. Department of Energy's (DOE)Carlsbad Area Office and the Westinghouse Waste Isolation Division (WID) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 1999 Site Environmental Report summarizes environmental data from calendar year 1999 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during calendar year 1999. WIPP received its first shipment of waste on March 26, 1999. In 1999, no evidence was found of any adverse effects from WIPP on the surrounding environment. Radionuclide concentrations in the environment surrounding WIPP were not statistically higher in 1999 than in 1998.

Waste Minimization Policy at the Romanian Nuclear Power Plant

International Nuclear Information System (INIS)

Andrei, V.; Daian, I.

2002-01-01

The radioactive waste management system at Cernavoda Nuclear Power Plant (NPP) in Romania was designed to maintain acceptable levels of safety for workers and to protect human health and the environment from exposure to unacceptable levels of radiation. In accordance with terminology of the International Atomic Energy Agency (IAEA), this system consists of the ''pretreatment'' of solid and organic liquid radioactive waste, which may include part or all of the following activities: collection, handling, volume reduction (by an in-drum compactor, if appropriate), and storage. Gaseous and aqueous liquid wastes are managed according to the ''dilute and discharge'' strategy. Taking into account the fact that treatment/conditioning and disposal technologies are still not established, waste minimization at the source is a priority environmental management objective, while waste minimization at the disposal stage is presently just a theoretical requirement for future adopted technologies . The necessary operational and maintenance procedures are in place at Cernavoda to minimize the production and contamination of waste. Administrative and technical measures are established to minimize waste volumes. Thus, an annual environmental target of a maximum 30 m3 of radioactive waste volume arising from operation and maintenance has been established. Within the first five years of operations at Cernavoda NPP, this target has been met. The successful implementation of the waste minimization policy has been accompanied by a cost reduction while the occupational doses for plant workers have been maintained at as low as reasonably practicable levels. This paper will describe key features of the waste management system along with the actual experience that has been realized with respect to minimizing the waste volumes at the Cernavoda NPP

Reverse osmosis: experience of cold commissioning trials in waste immobilisation plant, Trombay

International Nuclear Information System (INIS)

Anand, G.; Bose, Aditi; Verma, B.B.

1999-01-01

Industrial scale reverse osmosis plant for low level radioactive waste put up in Waste Immobilisation Plant (WIP), Trombay is the first of its kind in India. The performance test with inactive simulated waste is meeting the desired performance. The preliminary treatment of LLW stream at W.I.P., Trombay is proposed to be carried out with reverse osmosis membrane separation process. The design, recovery and rejection ratio of LLW is described

Pilot-plant development of a Rover waste calcination flowsheet

International Nuclear Information System (INIS)

Birrer, S.A.

1978-04-01

Results of eight runs, six using the 10-cm dia and two using the 30-cm dia pilot-plant calciners, in which simulated first-cycle Rover waste was calcined, are described. Results of the tests showed that a feed blend consisting of one volume simulated first-cycle Rover waste and one or two volumes simulated first-cycle zirconium waste could not be successfully calcined. 5 figs., 8 tables

Characterization of past and present solid waste streams from the Plutonium-Uranium Extraction Plant

International Nuclear Information System (INIS)

Pottmeyer, J.A.; Weyns, M.I.; Lorenzo, D.S.; Vejvoda, E.J.; Duncan, D.R.

1993-04-01

During the next two decades the transuranic wastes, now stored in the burial trenches and storage facilities at the Hanford Site, are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Over 7% of the transuranic waste to be retrieved for shipment to the Waste Isolation Pilot Plant has been generated at the Plutonium-Uranium Extraction (PUREX) Plant. The purpose of this report is to characterize the radioactive solid wastes generated by PUREX using process knowledge, existing records, and oral history interviews. The PUREX Plant is currently operated by the Westinghouse Hanford Company for the US Department of Energy and is now in standby status while being prepared for permanent shutdown. The PUREX Plant is a collection of facilities that has been used primarily to separate plutonium for nuclear weapons from spent fuel that had been irradiated in the Hanford Site's defense reactors. Originally designed to reprocess aluminum-clad uranium fuel, the plant was modified to reprocess zirconium alloy clad fuel elements from the Hanford Site's N Reactor. PUREX has provided plutonium for research reactor development, safety programs, and defense. In addition, the PUREX was used to recover slightly enriched uranium for recycling into fuel for use in reactors that generate electricity and plutonium. Section 2.0 provides further details of the PUREX's physical plant and its operations. The PUREX Plant functions that generate solid waste are as follows: processing operations, laboratory analyses and supporting activities. The types and estimated quantities of waste resulting from these activities are discussed in detail

Radioactive waste management plan for the PBMR (Pty) Ltd fuel plant

International Nuclear Information System (INIS)

Makgae, Mosidi E.

2009-01-01

The Pebble Bed Modular Reactor (Pty) Ltd Fuel Plant (PFP) radioactive waste management plan caters for waste from generation, processing through storage and possible disposal. Generally, the amount of waste that will be generated from the PFP is Low and Intermediate Level Waste. The waste management plan outlines all waste streams and the management options for each stream. It also discusses how the Plant has been designed to ensure radioactive waste minimisation through recycling, recovery, reuse, treatment before considering disposal. Compliance to the proposed plan will ensure compliance with national legislative requirements and international good practice. The national and the overall waste management objective is to ensure that all PFP wastes are managed appropriately by utilising processes that minimize, reduce, recover and recycle without exposing employees, the public and the environment to unacceptable impacts. Both International Atomic Energy Agency (IAEA) and Department of Minerals and Energy (DME) principles act as a guide in the development of the strategy in order to ensure international best practice, legal compliance and ensuring that the impact of waste on employees, environment and the public is as low as reasonably achievable. The radioactive waste classification system stipulated in the Radioactive Waste Management Policy and Strategy 2005 will play an important role in classifying radioactive waste and ensuring that effective management is implemented for all waste streams, for example gaseous, liquid or solid wastes.

Natural fiber-reinforced polymer composites

International Nuclear Information System (INIS)

Taj, S.; Khan, S.; Munawar, M.A.

2007-01-01

Natural fibers have been used to reinforce materials for over 3,000 years. More recently they have been employed in combination with plastics. Many types of natural fi fibers have been investigated for use in plastics including Flax, hemp, jute, straw, wood fiber, rice husks, wheat, barley, oats, rye, cane (sugar and bamboo), grass reeds, kenaf, ramie, oil palm empty fruit bunch, sisal, coir, water hyacinth, pennywort, kapok, paper-mulberry, raphia, banana fiber, pineapple leaf fiber and papyrus. Natural fibers have the advantage that they are renewable resources and have marketing appeal. The Asian markets have been using natural fibers for many years e.g., jute is a common reinforcement in India. Natural fibers are increasingly used in automotive and packaging materials. Pakistan is an agricultural country and it is the main stay of Pakistan's economy. Thousands of tons of different crops are produced but most of their wastes do not have any useful utilization. Agricultural wastes include wheat husk, rice husk, and their straw, hemp fiber and shells of various dry fruits. These agricultural wastes can be used to prepare fiber reinforced polymer composites for commercial use. This report examines the different types of fibers available and the current status of research. Many references to the latest work on properties, processing and application have been cited in this review. (author)

The risk of storing radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

Gruemm, H.

1976-09-01

Serious bottle-necks exist in the nuclear fuel cycle and will continue for the next decade. A total of 800 nuclear reactors are now in operation. 153 nuclear power plants represent an installed capacity of 70 GVe. Until 1985 five hundred nuclear power plants will be in operation from which up to this date 53.000 t uranium will have been discharged. Part of this will have to be reprocessed. Associated with the above mentioned amount are 500 t plutonium and 1.500 t highly radioactive wastes. Two risks for the population have to be considered: firstly, the effect of small amounts of radioactive substances released during normal operation of nuclear power plants (the annual dose is about 1 mrem per person). Secondly, the possibility of the release of great amounts of radioactivity during heavy accidents (the probability for which is extremely small). A series of feasible possibilities for conditioning are shown. Firstly, the wastes are packed in substances which are insoluble in water. Secondly, for low and medium wastes these can be mixed with concrete or bitumen and filled into stable containers. Thirdly, the wastes could also be solidified. Fourthly, the wastes could be enclosed in small glass spheres which are embedded in a metal matrix. (H.G.)

A new semi-mobile plant for radiation processing of waste

International Nuclear Information System (INIS)

Tata, A.

1998-04-01

A new pilot/demonstrative semi-mobile irradiation plant, named TRIRIS (TRIsaia-RIfiuti-Sterilizzazione, namely 'Trisaia Res. Center - Wastes- Sterilization') has been designed and erected. The plant goal is recognized in proposing and exploring new technological opportunities, based on an 'in-situ' effective processing of solid or liquid waste, mainly with reference to emergency situations (e.g. need of a quick environmental restoring operation following an accidental groundwater pollution). The project, which was jointly carried out by ENEA and Hitesys Co. and Italian electrons accelerators manufacturer, foresees a LINAC type EB-machine (s band) having 4-6 M e V and till 1000 W as beam features. Scattered radiation shielding is performed by a water pool surrounding the EB-machine head, filled up before operations. The plant, that is to be located at ENEA-Trisaia Res. Center (Basilicata southern of Italy), allows a large operative flexibility: groundwater and wastewater decontamination (1800 to 70 kg/h in the 1 to 25 kGy does range), organic and chlorinated waste streams (25 kg/h at 75 kGy), solid hospital wastes (50 kg/h at 35 kGy) or hazardous wastes like polycyclic aromatic compounds (180 to 35 kg/h in the 10 to 50 kGy dose range) [it

Plutonium finishing plant dangerous waste training plan

International Nuclear Information System (INIS)

ENTROP, G.E.

1999-01-01

This training plan describes general requirements, worker categories, and provides course descriptions for operation of the Plutonium Finish Plant (PFP) waste generation facilities, permitted treatment, storage and disposal (TSD) units, and the 90-Day Accumulation Areas

Myoglobin plasma level related to muscle mass and fiber composition: a clinical marker of muscle wasting?

Science.gov (United States)

Weber, Marc-André; Kinscherf, Ralf; Krakowski-Roosen, Holger; Aulmann, Michael; Renk, Hanna; Künkele, Annette; Edler, Lutz; Kauczor, Hans-Ulrich; Hildebrandt, Wulf

2007-08-01

Progressive muscle wasting is a central feature of cancer-related cachexia and has been recognized as a determinant of poor prognosis and quality of life. However, until now, no easily assessable clinical marker exists that allows to predict or to track muscle wasting. The present study evaluated the potential of myoglobin (MG) plasma levels to indicate wasting of large locomotor muscles and, moreover, to reflect the loss of MG-rich fiber types, which are most relevant for daily performance. In 17 cancer-cachectic patients (weight loss 22%) and 27 age- and gender-matched healthy controls, we determined plasma levels of MG and creatine kinase (CK), maximal quadriceps muscle cross-sectional area (CSA) by magnetic resonance imaging, muscle morphology and fiber composition in biopsies from the vastus lateralis muscle, body cell mass (BCM) by impedance technique as well as maximal oxygen uptake (VO(2)max). In cachectic patients, plasma MG, muscle CSA, BCM, and VO(2)max were 30-35% below control levels. MG showed a significant positive correlation to total muscle CSA (r = 0.65, p max as an important functional readout. CK plasma levels appear to be less reliable because prolonged increases are observed in even subclinical myopathies or after exercise. Notably, cancer-related muscle wasting was not associated with increases in plasma MG or CK in this study.

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.)

Radionuclide content of wastewater and solid waste from a low-level effluent treatment plant

International Nuclear Information System (INIS)

Muhamat Omar; Zalina Laili; Nik Marzukee Nik Ibrahim; Mat Bakar Mahusin

2010-01-01

A study on radioactivity levels of wastewater and solid waste from a Low-level Effluent Treatment Plant has been carried out. The measurement of radionuclide concentration was carried out using gamma spectrometry. Natural and anthropogenic radionuclides were detected in solid radioactive waste recovered from the treatment plant. The presence of radionuclides in waste water varies depending on activities carried out in laboratories and facilities connected to the plant. (author)

Characterization of past and present solid waste streams from the plutonium finishing plant

Energy Technology Data Exchange (ETDEWEB)

Duncan, D.R.; Mayancsik, B.A. [Westinghouse Hanford Co., Richland, WA (United States); Pottmeyer, J.A.; Vejvoda, E.J.; Reddick, J.A.; Sheldon, K.M.; Weyns, M.I. [Los Alamos Technical Associates, Kennewick, WA (United States)

1993-02-01

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing (WRAP) Facility, and shipped to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico for final disposal. Over 50% of the TRU waste to be retrieved for shipment to the WIPP has been generated at the Plutonium Finishing Plant (PFP), also known as the Plutonium Processing and Storage Facility and Z Plant. The purpose of this report is to characterize the radioactive solid wastes generated by the PFP since its construction in 1947 using process knowledge, existing records, and history-obtained from interviews. The PFP is currently operated by Westinghouse Hanford Company (WHC) for the US Department of Energy (DOE).

Characterization of past and present solid waste streams from the plutonium finishing plant

International Nuclear Information System (INIS)

Duncan, D.R.; Mayancsik, B.A.; Pottmeyer, J.A.; Vejvoda, E.J.; Reddick, J.A.; Sheldon, K.M.; Weyns, M.I.

1993-02-01

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing (WRAP) Facility, and shipped to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico for final disposal. Over 50% of the TRU waste to be retrieved for shipment to the WIPP has been generated at the Plutonium Finishing Plant (PFP), also known as the Plutonium Processing and Storage Facility and Z Plant. The purpose of this report is to characterize the radioactive solid wastes generated by the PFP since its construction in 1947 using process knowledge, existing records, and history-obtained from interviews. The PFP is currently operated by Westinghouse Hanford Company (WHC) for the US Department of Energy (DOE)

Cellulose fibers: bio- and nano-polymer composites ; green chemistry and technology

National Research Council Canada - National Science Library

Kalia, Susheel; Kaith, B. S; Inderjeet Kaur

2011-01-01

... on eco-friendly materials, and the steps taken in this direction will lead toward GreenScience and Green-Technology. Cellulosics account for about half of the dry weight of plant biomass and approximately half of the dry weight of secondary sources of waste biomass. At this crucial moment, cellulose fibers are pushed due to their "gr...

Vitrification of liquid waste from nuclear power plants

International Nuclear Information System (INIS)

Sheng Jiawei; Choi, Kwansik; Song, Myung-Jae

2001-01-01

Glass is an acceptable waste form to solidify the low-level waste from nuclear power plants (NPPs) because of the simplicity of processing and its unique ability to accept a wide variety of waste streams. Vitrification is being considered to solidify the high-boron-containing liquid waste generated from Korean NPPs. This study dealt with the development of a glass formulation to solidify the liquid waste. Studies were conducted in a borosilicate glass system. Crucible studies have been performed with surrogate waste. Several developed glass frits were evaluated to determine their suitability for vitrifying the liquid waste. The results indicated that the 20 wt% waste oxides loading required could not be obtained using these glass frits. Flyash produced from coal-burning electric power stations, whose major components are SiO 2 and Al 2 O 3 , is a desirable glass network former. Detailed product evaluations including waste loading, homogeneity, chemical durability and viscosity, etc., were carried out on selected formulations using flyash. Up to 30 wt% of the waste oxides was successfully solidified into the flyash after the addition of 5-10 wt% Na 2 O at 1200 deg. C

Nuclear power plants waste management practices in France

International Nuclear Information System (INIS)

Matsuda, Fumio

1998-01-01

This survey offers a complete review concerning the nuclear power plants waste management in France from generation to disposal, as well as future evolutions. Fundamental Safety Rule specified by the government defines safety objectives, design bases for surface disposals and preliminary terms for acceptance of waste packages on the surface disposal site. A governmental decree authorizes the creation of CSA (Centre de Stockage de l'Aude; French surface repository), and defines the limits of radiological inventory of the disposal facility. The national waste agency ANDRA was established in 1979 by government (turned into public in 1991), and ANDRA defines the technical specifications involving acceptance criteria of the waste packages. The main feature of the French management includes; Comprehensive quality assurance program that encompasses all area of the management. Centralized installation for the melting of contaminated scrap metals and incineration of low level technological wastes. Mobile unit for common treatment of ion exchange resin. Concrete package assuring the long term containment. Complete tracking system of wastes from generation to disposal. This survey would be useful in the consideration of Japanese waste management including miscellaneous wastes, high βγ wastes, large metallic wastes, etc. (author)

Waste to energy plant operation under the influence of market and legislation conditioned changes

DEFF Research Database (Denmark)

Tomic, Tihomir; Dominkovic, Dominik Franjo; Pfeifer, Antun

2017-01-01

, waste-to-energy plants need to be adapted to market operation. This influence is tracked by the gate-fee volatility. The operation of the waste-to-energy plant on electricity markets is simulated by using EnergyPLAN and heat market is simulated in Matlab, based on hourly marginal costs. The results have......In this paper, gate-fee changes of the waste-to-energy plants are investigated in the conditions set by European Union legislation and by the introduction of the new heat market. Waste management and sustainable energy supply are core issues of sustainable development of regions, especially urban...... areas. These two energy flows logically come together in the combined heat and power facility by waste incineration. However, the implementation of new legislation influences quantity and quality of municipal waste and operation of waste-to-energy systems. Once the legislation requirements are met...

Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

International Nuclear Information System (INIS)

1991-01-01

This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). This experimental-waste characterization program is only one part of the WIPP Test Phase, both in the short- and long-term, to quantify and evaluate the characteristics and behavior of transuranic (TRU) wastes in the repository environment. Other parts include the bin-scale and alcove tests, drum-scale tests, and laboratory experiments. In simplified terms, the purpose of the Program is to provide chemical, physical, and radiochemical data describing the characteristics of the wastes that will be emplaced in the WIPP, while the remaining WIPP Test Phase is directed at examining the behavior of these wastes in the repository environment. 50 refs., 35 figs., 33 tabs

Incorporation of Savannah River Plant radioactive waste into concrete

International Nuclear Information System (INIS)

Stone, J.A.

1975-01-01

Results are reported of a laboratory-scale experimental program at the Savannah River Laboratory to gain information on the fixation of high-level radioactive wastes in concrete. Two concrete formulations, a High-Alumina Cement and a Portland Pozzalanic cement, were selected on the bases of leachability and compressive strength for the fixation of non-radioactive simulated wastes. Therefore, these two cements were selected for current studies for the fixation of actual Savannah River Plant high-level wastes. (U.S.)

Municipal Waste-to-Energy plants in Poland – current projects

Directory of Open Access Journals (Sweden)

Cyranka Maciej

2016-01-01

Conclusions show why in the current situation development of Polish WtE infrastructure is right, i.e. operation of aforementioned plants that will ensure benefits associated with energy production, reduction of landfilling and informing public opinion regarding modern waste management models. Additionally, the article draws attention on the high responsibility that will be put on WtE plants operators and that experience gained during WtE implementation can be used to improve even further for future Polish Waste Management Systems.

Status of Pantex Plant Waste Management Project/program control system

International Nuclear Information System (INIS)

Price, Wesley J.; Matthews, William L.

1992-01-01

During a December 1990 Waste Management Program Review held in Albuquerque, New Mexico, the Waste Management and Operational Surety Division (WMOSD) introduced the project control system to be used for the Waste Management (WM) Operations Program. The system was entitled 'TRAC-WM' (Tracking and Control for Waste Management). The stated objective for this system was to establish a frame work for planning, managing, and controlling work within the WM program. As a result Mason and Hanger (the operating contractor at the Pantex Plant) initiated the development of a computerized waste management project tracking system. (author)

Evaluation of the content of neutral detergent fiber and acid through different procedures applied to forage plants

Directory of Open Access Journals (Sweden)

Luiz Juliano Valério Geron

2014-06-01

Full Text Available This study aimed to evaluate the content of neutral detergent fiber (NDF and acid (FDA of Marandu, Humidicula; Massai; Mombaça grass obtained by three different procedures with the conventional method (CON, the Filter Bag Technique Ankom® (FBT and adapted by EMBRAPA (EMB. The forage plants were obtained in the Southwest region of Mato Grosso in the September; the samples were collected from pastures planted the three years. There were three batteries (runs for each procedure (method for the determination of NDF and ADF of different forages. There were realised three batteries (runs for each procedure (method for the determination of NDF and ADF of different forages. We used a completely randomized design with three replications for each methodology. Statistical analysis of the variables studied was performed by analysis of variance and the differences obtained were analyzed by Tukey test, considering 5% significance level. It was observed that the different procedures (CON, FBT and EMB to determine the content NDF did not differ between them for different forages plants, with average values of 78.61% and 74.96% for the Marandu and Humidicula grass, respectively and 76.78% and 73.08% for Massai and Mombaça grass, respectively. The ADF content obtained by different procedures (CON, FBT and EMB showed no difference between them, with average values of 50.95% and 44.86% for Marandu and Humidicula grass, respectively and 52.21% and 51.56% for Massai and Mombaça grass, respectively. Thus, it is concluded that the content of neutral detergent fiber and acid Marandu, Humidicula; Massai and Mombaça grass can be determined by the procedure adapted by EMBRAPA, since this was not different compared to conventional methodology and the Filter Bag Technique Ankom®, besides having a lower waste of reagents and consequently lower cost.

Saltstone: cement-based waste form for disposal of Savannah River Plant low-level radioactive salt waste

International Nuclear Information System (INIS)

Langton, C.A.

1984-01-01

Defense waste processing at the Savannah River Plant will include decontamination and disposal of approximately 400 million liters of waste containing NaNO 3 , NaOH, Na 2 SO 4 , and NaNO 2 . After decontamination, the salt solution is classified as low-level waste. A cement-based waste form, saltstone, has been designed for disposal of Savannah River Plant low-level radioactive salt waste. Bulk properties of this material have been tailored with respect to salt leach rate, permeability, and compressive strength. Microstructure and mineralogy of leached and unleached specimens were characterized by SEM and x-ray diffraction analyses. The disposal system for the DWPF salt waste includes reconstitution of the crystallized salt as a solution containing 32 wt % solids. This solution will be decontaminated to remove 137 Cs and 90 Sr and then stabilized in a cement-based waste form. Laboratory and field tests indicate that this stabilization process greatly reduces the mobility of all of the waste constitutents in the surface and near-surface environment. Engineered trenches for subsurface burial of the saltstone have been designed to ensure compatibility between the waste form and the environment. The total disposal sytem, saltstone-trench-surrounding soil, has been designed to contain radionuclides, Cr, and Hg by both physical encapsulation and chemical fixation mechanisms. Physical encapsulation of the salts is the mechanism employed for controlling N and OH releases. In this way, final disposal of the SRP low-level waste can be achieved and the quality of the groundwater at the perimeter of the disposal site meets EPA drinking water standards

FIBER OPTICAL MICRO-DETECTORS FOR OXYGEN SENSING IN POWER PLANTS

International Nuclear Information System (INIS)

Baker, Gregory L.; Ghosh, Ruby N.; Osborn, D.J. III

2004-01-01

A reflection mode fiber optic oxygen sensor that can operate at high temperatures for power plant applications is being developed. The sensor is based on the 3 O 2 quenching of the red emission from hexanuclear molybdenum chloride clusters. High temperature measurements of the emission of clusters in sol gel films show that the luminescence intensity from the films follow a 1/T relationship from room temperature to 150 C, and then declines at a slower rate at higher temperatures. The large number of photons available at 230 C is consistent with simple low cost optics for fiber optic probes based on the emission from clusters in sol gel films

Microbiological air quality in an urban solid waste selection plant

Directory of Open Access Journals (Sweden)

Angela Del Cimmuto

2010-03-01

Full Text Available

Background: Exposure to bioaerosols may pose health risks to workers operating in the processing of Urban Solid Waste (USW. The aim of this study is to evaluate microbiological air quality within an USW selection facility.

Methods: Nine sampling points in an USW selection plant situated in central-southern Italy were selected. One outdoor sampling point provided the background data. Sampling was performed on a yearly basis (2005 – 2009 upon request by the management of the selection plant. Total Mesophilic Counts (TMC, as well as fungal and Gram-negative concentrations were determined.

Results: The highest viable fungal particles concentrations (medians were found in waste delivery areas (about 20000 CFU/m3, while the lowest were found in the control rooms (485 – 967 CFU/m3. TMC (median was highest (6116 CFU/m3 at the delivery pit, followed by the machine shop (3147 CFU/m3, where no waste processing takes place. Medians of Gram-negative bacteria are below the suggested Occupational Exposure Limit of 1000 CFU/m3, although this limit was exceeded at several single time-points in the waste delivery areas, and also in a personnel resting room. The lowest Gram-negative contamination was found in the control rooms (medians <1 CFU/m3.

Conclusions: Some areas within a USW selection plant act as internal sources of contamination towards those areas where partially processed waste, or no waste at all, is present. Well-designed air flows, or carefullythought positioning of areas that are not directly involved in waste processing are necessary and effective in obtaining

A waste to energy plant for an industrial districts

International Nuclear Information System (INIS)

Floreani, M.; Meneghetti, A.; Nardin, G.; Rocco, A.

2001-01-01

Industrial districts show characteristics that can be exploited by developing plant solutions studied for their special configuration and not simply extended from single unit models. In the paper a waste-to-energy plant for the chair industrial district in Friuli Venezia Giulia (North Eastern Italy) is described. It has been designed directly involving the University of Udine and can be considered an example of how technology innovation can be promoted by universities, especially in the case of small firms which have limited R and D resources. It is shown how industrial refuse becomes a chance of competitive advantage for the whole district due to its energy recovery in a plant unique for the type of waste processed. Input, combustion, energy recovery and cleaning sections are described in details, underlining innovative approaches and solutions [it

Waste heat recovery options in a large gas-turbine combined power plant

Science.gov (United States)

Upathumchard, Ularee

This study focuses on power plant heat loss and how to utilize the waste heat in energy recovery systems in order to increase the overall power plant efficiency. The case study of this research is a 700-MW natural gas combined cycle power plant, located in a suburban area of Thailand. An analysis of the heat loss of the combustion process, power generation process, lubrication system, and cooling system has been conducted to evaluate waste heat recovery options. The design of the waste heat recovery options depends to the amount of heat loss from each system and its temperature. Feasible waste heat sources are combustion turbine (CT) room ventilation air and lubrication oil return from the power plant. The following options are being considered in this research: absorption chillers for cooling with working fluids Ammonia-Water and Water-Lithium Bromide (in comparison) and Organic Rankine Cycle (ORC) with working fluids R134a and R245fa. The absorption cycles are modeled in three different stages; single-effect, double-effect and half-effect. ORC models used are simple ORC as a baseline, ORC with internal regenerator, ORC two-phase flash expansion ORC and ORC with multiple heat sources. Thermodynamic models are generated and each system is simulated using Engineering Equation Solver (EES) to define the most suitable waste heat recovery options for the power plant. The result will be synthesized and evaluated with respect to exergy utilization efficiency referred as the Second Law effectiveness and net output capacity. Results of the models give recommendation to install a baseline ORC of R134a and a double-effect water-lithium bromide absorption chiller, driven by ventilation air from combustion turbine compartment. The two technologies yield reasonable economic payback periods of 4.6 years and 0.7 years, respectively. The fact that this selected power plant is in its early stage of operation allows both models to economically and effectively perform waste heat

Low-level waste minimization at the Y-12 Plant

Energy Technology Data Exchange (ETDEWEB)

Koger, J. [Oak Ridge National Lab., TN (United States)

1993-03-01

The Y-12 Development Waste Minimization Program is used as a basis for defining new technologies and processes that produce minimum low-level wastes (hazardous, mixed, radioactive, and industrial) for the Y-12 Plant in the future and for Complex-21 and that aid in decontamination and decommissioning (D and D) efforts throughout the complex. In the past, the strategy at the Y-12 Plant was to treat the residues from the production processes using chemical treatment, incineration, compaction, and other technologies, which often generated copious quantities of additional wastes and, with the exception of highly valuable materials such as enriched uranium, incorporated very little recycle in the process. Recycle, in this context, is defined as material that is put back into the process before it enters a waste stream. Additionally, there are several new technology drivers that have recently emerged with the changing climate in the Nuclear Weapons Complex such as Complex 21 and D and D technologies and an increasing number of disassemblies. The hierarchies of concern in the waste minimization effort are source reduction, recycle capability, treatment simplicity, and final disposal difficulty with regard to Complex 21, disassembly efforts, D and D, and, to a lesser extent, weapons production. Source reduction can be achieved through substitution of hazardous substances for nonhazardous materials, and process changes that result in less generated waste.

Final environmental impact statement. Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1980-10-01

This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures are given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described

Removal of dissolved and suspended radionuclides from Hanford Waste Vitrification Plant liquid wastes

International Nuclear Information System (INIS)

Sharp, S.D.; Nankani, F.D.; Bray, L.A.; Eakin, D.E.; Larson, D.E.

1990-12-01

It was determined during Preliminary Design of the Hanford Waste Vitrification Plant that certain intermediate process liquid waste streams should be decontaminated in a way that would permit the purge of dissolved chemical species from the process recycle shop. This capability is needed to ensure proper control of product glass chemical composition and to avoid excessive corrosion of process equipment. This paper discusses the process design of a system that will remove both radioactive particulates and certain dissolved fission products from process liquid waste streams. Supporting data obtained from literature sources as well as from laboratory- and pilot-scale tests are presented. 3 refs., 1 fig., 3 tabs

Disposal of Savannah River Plant waste salt

International Nuclear Information System (INIS)

Dukes, M.D.

1982-01-01

Approximately 26-million gallons of soluble low-level waste salts will be produced during solidification of 6-million gallons of high-level defense waste in the proposed Defense Waste Processing Facility (DWPF) at the Savannah River Plant (SRP). Soluble wastes (primarily NaNO 3 , NaNO 2 , and NaOH) stored in the waste tanks will be decontaminated by ion exchange and solidified in concrete. The resulting salt-concrete mixture, saltcrete, will be placed in a landfill on the plantsite such that all applicable federal and state disposal criteria are met. Proposed NRC guidelines for the disposal of waste with the radionuclide content of SRP salt would permit shallow land burial. Federal and state rules require that potentially hazardous chemical wastes (mainly nitrate-nitrate salts in the saltcrete) be contained to the degree necessary to meet drinking water standards in the ground water beneath the landfill boundary. This paper describes the proposed saltcrete landfill and tests under way to ensure that the landfill will meet these criteria. The work includes laboratory and field tests of the saltcrete itself, a field test of a one-tenth linear scale model of the entire landfill system, and a numerical model of the system

Sampling and transport of paraffin waste form from CWDS of nuclear power plant

International Nuclear Information System (INIS)

Lee, J. M.; Hwang, J. H.; Kim, C. R.; Park, J. W.

2000-01-01

Sampling and transport of paraffin waste form from concentrated waste drying system (CWDS) of domestic nuclear power plant were performed to collect the leaching characteristic data for the disposal of radioactive waste. Transport was performed according to the national regulations and the internal rules of the nuclear power plant. The sample of paraffin waste form was classified as L type package according to the regulation and radiation exposure of operator was measured in the range of 6 to 12 mrem that was less than the estimated amount

New solutions for waste management centers of new Russian-type nuclear power plant designs

International Nuclear Information System (INIS)

Buettner, Klaus

2010-01-01

There has been a change of mind with respect to waste management among power plant operators in Russia and planners of the new VVER reactor line. Solid waste no longer is to be stored on the site of the power plant; instead, a functioning direct method of treatment of the different categories of waste arising in operation is favored. Waste conditioning and reduced storage volumes are indispensable arguments in selling reactor technology to markets outside Russia. Reference often is made to the internationally discussed volume of 50 m 3 of waste per reactor unit and year, which is then defined as a target. NUKEM Technologies verified existing technical concepts and worked out proposals of improved waste management. One project proposal accepted by ASE (Atomstroyexport) was elaborated to the Technical Project (corresponding to Basic Design) status. Specific management of materials flows, the use of processes tailored to the waste stream, and adaptation of the throughputs of these plants to the waste arisings actually expected are able to reduce clearly both the volume of conditioned waste to be stored and the capital costs. (orig.)

Mechanical Properties of Oil Palm Empty Fruit Bunch Fiber

Science.gov (United States)

Gunawan, Fergyanto E.; Homma, Hiroomi; Brodjonegoro, Satryo S.; Hudin, Afzer Bin Baseri; Zainuddin, Aryanti Binti

In tropical countries such as Indonesia and Malaysia, the empty fruit bunches are wastes of the oil palm industry. The wastes are abundantly available and has reached a level that severely threats the environment. Therefore, it is a great need to find useful applications of those waste materials; but firstly, the mechanical properties of the EFB fiber should be quantified. In this work, a small tensile test machine is manufactured, and the tensile test is performed on the EFB fibers. The results show that the strength of the EFB fiber is strongly affected by the fiber diameter; however, the fiber strength is relatively low in comparison to other natural fibers.

Innovative waste treatment and conditioning technologies at nuclear power plants

International Nuclear Information System (INIS)

2006-05-01

The objective of this publication is to provide Member States with information on the most innovative technologies and strategies used in waste treatment and conditioning. At present, some of those technologies and strategies might not be widely implemented at nuclear power plants (NPP), but they have an important potential for their use as part of the long range NPP, utility, or national strategy. Thus, the target audience is those decision makers at the national and organizational level responsible for selecting waste processing technologies and strategies over a period of three to ten years. Countries and individual nuclear plants have limited financial resources which can be applied toward radioactive waste processing (treatment and conditioning). They are challenged to determine which of the many available technologies and strategies are best suited to meet national or local needs. This publication reduces the selection of processes for wastes generated by nuclear power plants to those technologies and strategies which are considered innovative. The report further identifies the key benefits which may derive from the adoption of those technologies, the different waste streams to which each technology is relevant, and the limitations of the technologies. The technologies and strategies identified have been evaluated to differentiate between (1) predominant technologies (those that are widely practiced in multiple countries or a large number of nuclear plants), and (2) innovative technologies (those which are not so widely used but are considered to offer benefits which make them suitable for broader application across the industry). Those which fall into the second category are the primary focus of this report. Many IAEA publications address the technical aspects of treatment and conditioning for radioactive wastes, covering research, technological advances, and safety issues. These studies and reports primarily target the research and technical staff of a

Effect of incubation time of sago (metroxylon sago) waste by local microorganism ″ginta″ on ph, crude protein, and crude fiber content

Science.gov (United States)

Ginting, Nurzainah; Pase, E.

2018-03-01

This study aims to examine the effect of incubation times of sago waste by local microorganism (MOL) “Ginta” to the crude protein and crude fiber content in relation to finding a cheap and good quality ruminants feed alternative. Incubation times were 0 hours to 144 hours. The data obtained were analyzed using Completely Randomize Design consisting of seven treatments and three replications. The result showed that the duration of incubation of sago waste by local microorganism (MOL) “Ginta” caused pH reduction, improved crude protein and crude fiber content. pH reduction was from 7.03 at 0 hour to 4.05 at 144 hours incubation. The highest increased in crude protein was H6U3 (5.58%) : 144 hours incubation and the lowest was H0U2 (3.22%) : 0 hour incubation while the highest crude fiber was H0U1 (19.99%) : 0 hour incubation and the lowest was H6U3 (18.23%) : 144 hours incubation. It can be concluded that incubation of sago waste triggered lower pH, higher crude protein and lower crude fiber than uninoculated. A recommendation could be given on using MOL ‘Ginta” in order to produce a cheap and good quality ruminans feed alternative.

Defense waste salt disposal at the Savannah River Plant

International Nuclear Information System (INIS)

Langton, C.A.; Dukes, M.D.

1984-01-01

A cement-based waste form, saltstone, has been designed for disposal of Savannah River Plant low-level radioactive salt waste. The disposal process includes emplacing the saltstone in engineered trenches above the water table but below grade at SRP. Design of the waste form and disposal system limits the concentration of salts and radionuclides in the groundwater so that EPA drinking water standards will not be exceeded at the perimeter of the disposal site. 10 references, 4 figures, 3 tables

Waste isolation pilot plant disposal room model

Energy Technology Data Exchange (ETDEWEB)

Butcher, B.M.

1997-08-01

This paper describes development of the conceptual and mathematical models for the part of the Waste Isolation Pilot Plant (WIPP) repository performance assessment that is concerned with what happens to the waste over long times after the repository is decommissioned. These models, collectively referred to as the {open_quotes}Disposal Room Model,{close_quotes} describe the repository closure process during which deformation of the surrounding salt consolidates the waste. First, the relationship of repository closure to demonstration of compliance with the Environmental Protection Agency (EPA) standard (40 CFR 191 Appendix C) and how sensitive performance results are to it are examined. Next, a detailed description is provided of the elements of the disposal region, and properties selected for the salt, waste, and other potential disposal features such as backfill. Included in the discussion is an explanation of how the various models were developed over time. Other aspects of closure analysis, such as the waste flow model and method of analysis, are also described. Finally, the closure predictions used in the final performance assessment analysis for the WIPP Compliance Certification Application are summarized.

Waste isolation pilot plant disposal room model

International Nuclear Information System (INIS)

Butcher, B.M.

1997-08-01

This paper describes development of the conceptual and mathematical models for the part of the Waste Isolation Pilot Plant (WIPP) repository performance assessment that is concerned with what happens to the waste over long times after the repository is decommissioned. These models, collectively referred to as the open-quotes Disposal Room Model,close quotes describe the repository closure process during which deformation of the surrounding salt consolidates the waste. First, the relationship of repository closure to demonstration of compliance with the Environmental Protection Agency (EPA) standard (40 CFR 191 Appendix C) and how sensitive performance results are to it are examined. Next, a detailed description is provided of the elements of the disposal region, and properties selected for the salt, waste, and other potential disposal features such as backfill. Included in the discussion is an explanation of how the various models were developed over time. Other aspects of closure analysis, such as the waste flow model and method of analysis, are also described. Finally, the closure predictions used in the final performance assessment analysis for the WIPP Compliance Certification Application are summarized

Waste from nuclear power plants

International Nuclear Information System (INIS)

1980-01-01

The report presents proposals for organizing and financing of the treatment and deposition of spent fuel and radioactive waste. Decommissioning of plants is taken into consideration. The proposals refer to a program of twelve reactors. A relatively complete model for the handling of radioactive waste in Sweden is at hand. The cost for the years 1980 to 2000 is estimated at approx 1040 million SKr. Also the expense to dispose of the rest of the waste is calculated up to the year 2060, when the waste is planned to be put into final deposit. The state must have substantial influence over the organization which should be closely connected to the nuclear industry. Three different types of organization are discussed, namely (i) a company along with a newly created authority, (ii) a company along with the existing Nuclear Power Inspectorate or (iii) a company along with a board of experts. The proposals for financing the cost of handling nuclear waste are given in chief outlines. The nuclear industry should reserve means to special funds. The allocations are calculated to 1.4 oere per delivered kWh up to and including the year 1980. The accumulated allocations for 1979 should thus amount to 1310 million SKr. The charge for supervision and for certain research and development is recommended to be 0.1 oere per kWh which corresponds to approx 23 million SKr for 1980. The funds should be assured by binding agreements which must be approved by the state. The amounts are given in the monetary value of the year 1979. (G.B.)

Waste treatment of ships. Change in understanding of wastes and trend of waste treatment systems; Senjo no haikibutsu shori. 1. Haikibutsu ni taisuru ninshiki no henka to shori hoshiki no doko

Energy Technology Data Exchange (ETDEWEB)

Inatomi, M. [Hitachi Zosen Corp., Osaka (Japan)

1996-07-25

This paper explains treatment of wastes produced in ships. Wastes produced in ships should be essentially treated on ships. Since storage and transport of difficult-to-treat wastes to harbor for land treatment is expensive, wastes produced in ships are treated on ships as much as possible. Combustibles such as waste oil, plastics, paper and wood fiber waste are treated by incinerator. Food waste is dumped into the sea after crushing by disposer. Excrement and urine are dumped into the sea through a waste water treatment plant. Oil content in oily bilge is burned after heating and vapor separation. Food waste is temporarily stored in ships because its dumping along the coast and into harbor is impossible. Kitchen refuse decomposer utilizing bacteria was proposed for ships. Press for used cans and crushing/thermal compaction/storage equipment for plastics were also put on the market. The primary regulation on diesel engine exhaust gas may be cleared by improvement of engine bodies. 1 ref., 1 fig., 1 tab.

Management of effluents and radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

2005-01-01

Management of effluents and radioactive waste from nuclear power plants, from the viewpoint of radiological protection, basically consists of three main themes: 1) developing and implementing actions that minimize, or where possible, eliminate generation. These actions ranging from simple awareness of people involved with the work on project modifications; 2) maintain a system of accounting and control that allows to know the characteristics of effluents and wastes, charting indicators that reveal the performance and trends of plant, and supplying data proving the compliance of national regulatory body standards; 3) Storing the solid waste generated in a safe manner, ensuring that the physical integrity of the packaged is maintained and that there is no impact to the population and the environment

An overview of U.S. plant performance improvement through effective radioactive waste management

International Nuclear Information System (INIS)

Sieberling, R.; Lyons, P.W.

1986-01-01

Radioactive waste volumes in the United States commercial nuclear power industry have declined over the last five years after increasing steadily in the late 1970's. This decline is considered to be especially significant because major backfits/modifications and major component repair/replacement at U.S. nuclear power stations have been accomplished during this period. This paper analyzes the key reasons for this performance and outlines the positive effects that this trend has upon overall nuclear plant performance. In reviewing plant performance data, there appears to be a direct correlation between overall plant performance and radioactive waste performance. For example, plants with high capacity factors, strong industrial safety programs, low collective man-rem, and good contamination controls, generally have a history of low radioactive waste volumes. The reasons for this excellent performance is the result of direct management and supervisory involvement in plant operations, implementation of high standards of performance, and monitoring performance against these standards. Using the techniques outlined in this paper, the U.S. nuclear power industry can continue to reduce the volume of low-level solid radioactive waste being generated

Critical components of odors in evaluating the performance of food waste composting plants

International Nuclear Information System (INIS)

Mao, I-F.; Tsai, C.-J.; Shen, S.-H.; Lin, T.-F.; Chen, W.-K.; Chen, M.-L.

2006-01-01

The current Taiwan government policy toward food waste management encourages composting for resource recovery. This study used olfactometry, gas chromatography-mass spectrometry (GC-MS) and gas detector tubes to evaluate the ambient air at three of the largest food waste composting plants in Taiwan. Ambient air inside the plants, at exhaust outlets and plant boundaries was examined to determine the comprehensive odor performance, critical components, and odor elimination efficiencies of various odor control engineering. Analytical results identified 29 compounds, including ammonia, amines, acetic acid, and multiple volatile organic compounds (VOCs) (hydrocarbons, ketones, esters, terpenes and S-compounds) in the odor from food waste composting plants. Concentrations of six components - ammonia, amines, dimethyl sulfide, acetic acid, ethyl benzene and p-Cymene - exceeded human olfactory thresholds. Ammonia, amines, dimethyl sulfide and acetic acid accounted for most odors compared to numerous VOCs. The results also show that the biotrickling filter was better at eliminating the concentrations of odor, NH 3 , amines, S-compounds and VOCs than the chemical scrubber and biofilters. All levels measured by olfactometry at the boundaries of food waste composting plants (range, 74-115 Odor Concentration (OC)) exceeded Taiwan's EPA standard of 50 OC. This study indicated that the malodor problem continued to be a significant problem for food waste recovery

Critical components of odors in evaluating the performance of food waste composting plants

Energy Technology Data Exchange (ETDEWEB)

Mao, I-F. [Institute of Environmental Health Sciences, National Yang-Ming University, No. 155, Sec.2, Li-Nong St., Beitou, Taipei, Taiwan (China)]. E-mail: ifmao@ym.edu.tw; Tsai, C.-J. [Institute of Environmental Health Sciences, National Yang-Ming University, No. 155, Sec.2, Li-Nong St., Beitou, Taipei, Taiwan (China); Shen, S.-H. [Department of Environment Management, Jin Wen Institute of Technology, No. 99, An-Chung Rd., Hsin-Tien City, Taipei, Taiwan (China); Lin, T.-F. [Institute of Environmental Engineering, National Cheng Kung University, No. 1, Ta-Hsueh Rd., Tainan, Taiwan (China); Chen, W.-K. [Department of Environment Management, Jin Wen Institute of Technology, No. 99, An-Chung Rd., Hsin-Tien City, Taipei, Taiwan (China); Chen, M.-L. [Institute of Environmental Health Sciences, National Yang-Ming University, No. 155, Sec.2, Li-Nong St., Beitou, Taipei, Taiwan (China)]. E-mail: mlchen@ym.edu.tw

2006-11-01

The current Taiwan government policy toward food waste management encourages composting for resource recovery. This study used olfactometry, gas chromatography-mass spectrometry (GC-MS) and gas detector tubes to evaluate the ambient air at three of the largest food waste composting plants in Taiwan. Ambient air inside the plants, at exhaust outlets and plant boundaries was examined to determine the comprehensive odor performance, critical components, and odor elimination efficiencies of various odor control engineering. Analytical results identified 29 compounds, including ammonia, amines, acetic acid, and multiple volatile organic compounds (VOCs) (hydrocarbons, ketones, esters, terpenes and S-compounds) in the odor from food waste composting plants. Concentrations of six components - ammonia, amines, dimethyl sulfide, acetic acid, ethyl benzene and p-Cymene - exceeded human olfactory thresholds. Ammonia, amines, dimethyl sulfide and acetic acid accounted for most odors compared to numerous VOCs. The results also show that the biotrickling filter was better at eliminating the concentrations of odor, NH{sub 3}, amines, S-compounds and VOCs than the chemical scrubber and biofilters. All levels measured by olfactometry at the boundaries of food waste composting plants (range, 74-115 Odor Concentration (OC)) exceeded Taiwan's EPA standard of 50 OC. This study indicated that the malodor problem continued to be a significant problem for food waste recovery.

Future-proof radioactive waste treatment technologies for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Buettner, Klaus; Braehler, Georg [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany)

2014-08-15

In order to select the optimal treatment method for radioactive waste three options can be considered. First, to treat the radioactive waste only to allow long term interim storage until the waste acceptance criteria are defined and the disposal sites are operable. Second, to select treatment methods just in compliance with the current state of discussion with the regard to the above. Third, taking also the future development in the field of waste acceptance criteria and disposal into account. When developing waste treatment systems for Nuclear Power Plants NUKEM Technologies follows the following targets, minimisation of the amount of radioactive waste, maximisation of free release material, volume reduction, avoidance of unwanted materials in the waste package, as well as efficient waste treatment solutions (low investment, high volume reduction). With its technologies produced waste packages fulfil the most stringent waste acceptance criteria.

Radioactive air emissions notice of construction and application for approval to construct the Hanford Waste Vitrification Plant

International Nuclear Information System (INIS)

1992-10-01

The Hanford Site is owned by the US Government and operated by the US Department of Energy, Richland Field Office. The Hanford Site manages and produces dangerous waste and mixed waste. (containing both radioactive and dangerous components). The US Department of Energy, Richland Field Office, currently stores mixed waste, resulting from various processing operations, in underground storage tanks. The Hanford Waste Vitrification Plant will be constructed and operated to process the high-activity fraction of mixed waste stored in these underground tanks. The Hanford Waste Vitrification Plant will solidify pretreated tank waste into a glass product that will be packaged for disposal in a national repository. Emissions from the Hanford Waste Vitrification Plant will be regulated by both the federal and state Clean Air Acts. The proposed Hanford Waste Vitrification Plant represents a new source of radioactive air emissions. Construction of the plant will require approval from both federal and state agencies. The Notice of Construction and Application for Approval to Construct the Hanford Waste Vitrification Plant contains information required under Title 40 of the Code of Federal Regulations, Chapter 61; and Chapter 246-247 of the Washington Administrative Code for a proposed new source of radioactive air emissions. The document contents are based on information contained in the Hanford Waste Vitrification Plant Reference Conceptual Design Report, the Hanford Waste Vitrification Plant Preliminary Safety Analysis Report, Revision 0, and subsequent design changes made before August 1, 1992. The contents of this document may be modified to include more specific information generated during subsequent detailed design phases. Modifications will be submitted for regulatory review and approval, as appropriate

Waste Isolation Pilot Plant 2001 Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Westinghouse TRU Solutions, Inc.

2002-09-20

The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment.

Waste Isolation Pilot Plant 2001 Site Environmental Report

International Nuclear Information System (INIS)

Westinghouse TRU Solutions, Inc.

2002-01-01

The United States (U.S.) Department of Energy's (DOE) Carlsbad Field Office (CBFO) and Westinghouse TRU Solutions LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2001 Site Environmental Report summarizes environmental data from calendar year (CY) 2001 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH- 0173T), and the Waste Isolation Pilot Plant Environmental Protection Implementation Plan (DOE/WIPP 96-2199). The above Orders and guidance documents require that DOE facilities submit an annual site environmental report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health; and the New Mexico Environment Department (NMED). The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2001. WIPP received its first shipment of waste on March 26, 1999. In 2001, no evidence was found of any adverse effects from WIPP on the surrounding environment

Six-year experiences in the operation of a low level liquid waste treatment plant

International Nuclear Information System (INIS)

Wen, S.-J.; Hwang, S.-L.; Tsai, C.-M.

1980-01-01

The operation of a low level liquid waste treatment plant is described. The plant is designed for the disposal of liquid waste produced primarily by a 40 MW Taiwan Research Reactor as well as a fuel fabrication plant for the CANDU type reactor and a radioisotopes production laboratory. The monthly volume treated is about 600-2500 ton of low level liquid waste. The activity levels are in the range of 10 -5 -10 -3 μCi/cm 3 . The continuous treatment system of the low level liquid waste treatment plant and the treatment data collected since 1973 are discussed. The advantages and disadvantages of continuous and batch processes are compared. In the continuous process, the efficiency of sludge treatment, vermiculite ion exchange and the adsorption of peat are investigated for further improvement. (H.K.)

Final environmental impact statement. Waste Isolation Pilot Plant

Energy Technology Data Exchange (ETDEWEB)

1980-10-01

This volume contains the appendices for the Final Environmental Impact Statement for the Waste Isolation Pilot Plant (WIPP). Alternative geologic environs are considered. Salt, crystalline rock, argillaceous rock, and tuff are discussed. Studies on alternate geologic regions for the siting of WIPP are reviewed. President Carter's message to Congress on the management of radioactive wastes and the findings and recommendations of the interagency review group on nuclear waste management are included. Selection criteria for the WIPP site including geologic, hydrologic, tectonic, physicochemical compatability, and socio-economic factors are presented. A description of the waste types and the waste processing procedures are given. Methods used to calculate radiation doses from radionuclide releases during operation are presented. A complete description of the Los Medanos site, including archaeological and historic aspects is included. Environmental monitoring programs and long-term safety analysis program are described. (DMC)

Decontamination of Savannah River Plant waste glass canisters

International Nuclear Information System (INIS)

Rankin, W.N.

1982-01-01

A Defense Waste Processing Facility (DWPF) is currently being designed to convert Savannah River Plant (SRP) liquid, high-level radioactive waste into a solid form, such as borosilicate glass. The outside of the canisters of waste glass must have very low levels of smearable radioactive contamination before they are removed from the DWPF to prevent the spread of radioactivity. Several techniques were considered for canister decontamination: high-pressure water spray, electropolishing, chemical dissolution, and abrasive blasting. An abrasive blasting technique using a glass frit slurry has been selected for use in the DWPF. No additional equipment is needed to process waste generated from decontamination. Frit used as the abrasive will be mixed with the waste and fed to the glass melter. In contrast, chemical and electrochemical techniques require more space in the DWPF, and produce large amounts of contaminated byproducts which are difficult to immobilize by vitrification

Municipal Solid Waste Gasification Plant Integrated With SOFC and Gas Turbine

DEFF Research Database (Denmark)

Bellomare, Filippo; Rokni, Masoud

2012-01-01

An interesting source of producing energy with low pollutants emission and reduced environmental impact are the biomasses; particularly using Municipal Solid Waste (MSW) as fuel, can be a competitive solution not only to produce energy with negligible costs but also to decrease the storage...... in landfills. A Municipal Solid Waste Gasification Plant Integrated with Solid Oxide Fuel Cell (SOFC) and Gas Turbine (GT) has been studied and the plant is called IGSG (Integrated Gasification SOFC and GT). Gasification plant is fed by MSW to produce syngas by which the anode side of a SOFC is fed wherein...

Resource conversation and recovery act draft hazardous waste facility permit: Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

1993-08-01

Volume II contains attachments for Module II and Module III. Attachments for Module II are: part A permit application; examples of acceptable documentation; Waste Isolation Pilot Plant generator/storage site waste screening and acceptance audit program; inspection schedule and monitoring schedule; inspection log forms; personnel training course outlines; hazardous waste job position training requirements; contingency plan; closure plan; and procedures for establishing background for the underground units. One attachment, facility process information, is included for Module III. Remaining attachments for this module are in Volume III

Novel Fiber-Based Adsorbent Technology; FINAL

International Nuclear Information System (INIS)

Nixon, P.G.; Tsukamoto, T.; Brose, D.J.

2001-01-01

The overall of this Department of Energy (DOE) Phase II SBIR program was to develop a new class of highly robust fiber-based adsorbents for recovery of heavy metals from aqueous waste-streams. The fiber-based adsorbents,when commercialized,will be used for clean up metals in aqueous waste-streams emanating from DOE facilities,industry,mining,and groundwater-cleanup operations.The amount of toxic waste released by these streams is of great significance.The U.S.Environment Protection Agency (EPA) reports that in 1990 alone,4.8 billion pounds of toxic chemicals were released into the environment.Of this waste,the metals-containing waste was the second largest contributor,representing 569 million pounds. This report presents the results of the Phase II program,which successfully synthesized noval fiber-based adsorbents for the removal of Group 12 metals(i.e.mercury),Group 14 metals (lead),and Group 10 metals(platinum and palladium) from contaminated groundwater and industrial waste streams.These fiber-based adsorbents are ideally suited for the recovery of metal ions from aqueous waste streams presently not treatable due to the degrading nature of corrosive chemicals or radioactive components in the feed stream. The adsorbents developed in this program rely on chemically resistant and robust carbon fibers and fabrics as supports for metal-ion selective ligands.These adsorbents demonstrate loading capacities and selectivities for metal ions exceeding those of conventional ion-exchange resins.The adsorbents were also used to construct filter modules that demonstrate minimal fouling,minimal compaction,chemical and physical robustness,and regeneration of metal loading capacity without loss of performance

B Plant low level waste system integrity assessment report

International Nuclear Information System (INIS)

Walter, E.J.

1995-09-01

This document provides the report of the integrity assessment activities for the B Plant low level waste system. The assessment activities were in response to requirements of the Washington State Dangerous Waste Regulations, Washington Administrative Code (WAC), 173-303-640. This integrity assessment report supports compliance with Hanford Federal Facility Agreement and Consent Order interim milestone target action M-32-07-T03

Process description and plant design for preparing ceramic high-level waste forms

International Nuclear Information System (INIS)

Grantham, L.F.; McKisson, R.L.; Guon, J.; Flintoff, J.F.; McKenzie, D.E.

1983-01-01

The ceramics process flow diagram has been simplified and upgraded to utilize only two major processing steps - fluid-bed calcination and hot isostatic press consolidating. Full-scale fluid-bed calcination has been used at INEL to calcine high-level waste for 18 y; and a second-generation calciner, a fully remotely operated and maintained calciner that meets ALARA guidelines, started calcining high-level waste in 1982. Full-scale hot isostatic consolidation has been used by DOE and commercial enterprises to consolidate radioactive components and to encapsulate spent fuel elements for several years. With further development aimed at process integration and parametric optimization, the operating knowledge of full-scale demonstration of the key process steps should be rapidly adaptable to scale-up of the ceramic process to full plant size. Process flowsheets used to prepare ceramic and glass waste forms from defense and commercial high-level liquid waste are described. Preliminary layouts of process flow diagrams in a high-level processing canyon were prepared and used to estimate the preliminary cost of the plant to fabricate both waste forms. The estimated costs for using both options were compared for total waste management costs of SRP high-level liquid waste. Using our design, for both the ceramic and glass plant, capital and operating costs are essentially the same for both defense and commercial wastes, but total waste management costs are calculated to be significantly less for defense wastes using the ceramic option. It is concluded from this and other studies that the ceramic form may offer important advantages over glass in leach resistance, waste loading, density, and process flexibility. Preliminary economic calculations indicate that ceramics must be considered a leading candidate for the form to immobilize high-level wastes

INTELLIGENT DECISION SUPPORT FOR WASTE MINIMIZATION IN ELECTROPLATING PLANTS. (R824732)

Science.gov (United States)

AbstractWastewater, spent solvent, spent process solutions, and sludge are the major waste streams generated in large volumes daily in electroplating plants. These waste streams can be significantly minimized through process modification and operational improvement. I...

Savannah River Plant low-level waste incinerator demonstration

International Nuclear Information System (INIS)

Tallman, J.A.

1984-01-01

A two-year demonstration facility was constructed at the Savannah River Plant (SRP) to incinerate suspect contaminated solid and low-level solvent wastes. Since startup in January 1984, 4460 kilograms and 5300 liters of simulated (uncontaminated) solid and solvent waste have been incinerated to establish the technical and operating data base for the facility. Combustion safeguards have been enhanced, process controls and interlocks refined, some materials handling problems identified and operating experience gained as a result of the 6 month cold run-in. Volume reductions of 20:1 for solid and 25:1 for solvent waste have been demonstrated. Stack emissions (NO 2 , SO 2 , CO, and particulates) were only 0.5% of the South Carolina ambient air quality standards. Radioactive waste processing is scheduled to begin in July 1984. 2 figures, 2 tables

Encapsulation pilot plant of radioactive wastes in thermosetting resins

International Nuclear Information System (INIS)

1982-01-01

The thermosetting resins (polyesters, epoxides) are used to encapsulate the low and intermediate - level radioactive wastes. The testing program concerning the drums produced by the pilot plant of the Chooz nuclear power plant is described. The installation operating is examined while thinking of the industrial application. The production costs are then evaluated

The Challenges of Creating a Real-Time Data Management System for TRU-Mixed Waste at the Advanced Mixed Waste Treatment Plant

International Nuclear Information System (INIS)

Paff, S. W; Doody, S.

2003-01-01

This paper discusses the challenges associated with creating a data management system for waste tracking at the Advanced Mixed Waste Treatment Plant (AMWTP) at the Idaho National Engineering Lab (INEEL). The waste tracking system combines data from plant automation systems and decision points. The primary purpose of the system is to provide information to enable the plant operators and engineers to assess the risks associated with each container and determine the best method of treating it. It is also used to track the transuranic (TRU) waste containers as they move throughout the various processes at the plant. And finally, the goal of the system is to support paperless shipments of the waste to the Waste Isolation Pilot Plant (WIPP). This paper describes the approach, methodologies, the underlying design of the database, and the challenges of creating the Data Management System (DMS) prior to completion of design and construction of a major plant. The system was built utilizing an Oracle database platform, and Oracle Forms 6i in client-server mode. The underlying data architecture is container-centric, with separate tables and objects for each type of analysis used to characterize the waste, including real-time radiography (RTR), non-destructive assay (NDA), head-space gas sampling and analysis (HSGS), visual examination (VE) and coring. The use of separate tables facilitated the construction of automatic interfaces with the analysis instruments that enabled direct data capture. Movements are tracked using a location system describing each waste container's current location and a history table tracking the container's movement history. The movement system is designed to interface both with radio-frequency bar-code devices and the plant's integrated control system (ICS). Collections of containers or information, such as batches, were created across the various types of analyses, which enabled a single, cohesive approach to be developed for verification and

Improvement of the safety regulations in the management of radioactive waste accumulated in the liquid radioactive waste water basins of the PO 'Majak' (Ozersk), the Siberian Chemical Plant (Seversk) and the Mining-Chemical Plant (Zheleznogorsk)

International Nuclear Information System (INIS)

Vishnevski, Y.G.; Kislov, A.I.; Irushkin, V.M.

2002-01-01

One of the most important problems of radiation safety in Russia is the decommissioning of the liquid radioactive waste water basins of the PO 'Majak' (Ozersk), Siberian Chemical Plant (Seversk) and Mining-Chemical Plant (Zheleznogorsk). The liquid radioactive waste water basins were constructed in 1950-1960 for the collection and storage of liquid waste from the radiochemical plants. The potential hazards of the liquid in the radioactive waste water basins are: migration of radionuclides into the soil of the liquid radioactive waste water basin floors; wind-induced carry-over of radionuclides from the liquid radioactive waste water basins; hazards (radiation included) to the environment and population arising in case physical barriers and hydraulic structures are damaged; and criticality hazards. The classification of the liquid radioactive waste water basins were developed based on the collection and analyzes of the information on liquid radioactive waste water basin characteristics and the method of multicriterion expert assessment of potential hazards. Three main directions for the improvement of safety regulation in the management of radioactive waste accumulated in the liquid radioactive waste water basins were defined: 1. Common directions for the improvement of safety regulation in the area of rehabilitation of the territories contaminated with radioactive substances. 2. Common directions for the improvement of safety regulation in the area of rehabilitation of the territories, such as the liquid radioactive waste water basins. 3. Special directions for the regulatory activities in the area of operation and decommissioning of the liquid radioactive waste water basins of the PO 'Majak' (Ozersk), Siberian Chemical Plant (Seversk) and Mining-Chemical Plant (Zheleznogorsk). As a result, concrete recommendations on safety regulation for the management of radioactive waste accumulated in the water basins were developed. (author)

Operations Program Plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1990-09-01

This document, Revision 4 of the Operations Program Plan, has been developed as the seven-year master plan for operating of the Waste Isolation Pilot Plant (WIPP). Subjects covered include public and technical communications; regulatory and environmental programs; startup engineering; radiation handling, surface operations, and underground operations; waste certification and waste handling; transportation development; geotechnical engineering; experimental operations; engineering program; general maintenance; security program; safety, radiation, and regulatory assurance; quality assurance program; training program; administration activities; management systems program; and decommissioning. 243 refs., 19 figs., 25 tabs. (SM)

Kinetics of transit and degradation of the fiber from guinea grass silages enriched with waste from soybean pre-cleaning

Directory of Open Access Journals (Sweden)

Filipe Ton Fialho

2015-06-01

Full Text Available The objective was to study the kinetics of transit and degradation of the fiber from guinea grass and the waste from soybean pre-cleaning (WSPC, ensiled with different proportions of mass (0, 100, 150, and 200 g WSPC/kg total mass. Four crossbred (Gyr × Holstein, fistulated cattle with an average body mass of 400±50 kg were organized in a 4 × 4 Latin square experimental design. The fiber utilized in the study of the transit kinetics was stained with chromium mordant, whereas the in situ technique was adopted for the degradation kinetics. The level of inclusion of WSPC only affected the true digestibility and the mean retention time. The addition of waste from soybean pre-cleaning to the silage of guinea grass is beneficial, in terms of kinetics of digestion and passage, at up to levels close to 100 g/kg, because after this quantity the fiber digestion and passage in and through the reticulo-rumen are impaired and there may be alterations in the ruminal environment that will affect the use of silage by animals.

The effects of composting on the nutritional composition of fibrous bio-regenerative life support systems (BLSS) plant waste residues and its impact on the growth of Nile tilapia ( Oreochromis niloticus)

Science.gov (United States)

Gonzales, John M.; Lowry, Brett A.; Brown, Paul B.; Beyl, Caula A.; Nyochemberg, Leopold

2009-04-01

Utilization of bio-regenerative life support systems (BLSS) plant waste residues as a nutritional source by Nile tilapia ( Oreochromis niloticus) has proven problematic as a result of high concentrations of fibrous compounds in the plant waste residues. Nutritional improvement of plant waste residues by composting with the oyster mushroom ( Pleurotus ostreatus), and the effects on growth and nutrient utilization of Nile tilapia fed such residues were evaluated. Five Nile tilapia (mean weight = 70.9 ± 3.1 g) were stocked in triplicate aquaria and fed one of two experimental diets, cowpea (CP) and composted cowpea (CCP), twice daily for a period of 8 weeks. Composting of cowpea residue resulted in reduced concentrations of nitrogen-free extract, hemi-cellulose and trypsin inhibitor activity, though trypsin inhibitor activity remained high. Composting did not reduce crude fiber, lignin, or cellulose concentrations in the diet. No significant differences ( P tilapia fed CP and CCP. These results suggest that P. ostreatus is not a suitable candidate for culture in conjunction with the culture of Nile tilapia. Additional work is needed to determine what, if any, benefit can be obtained from incorporating composted residue as feed for Nile tilapia.

Estimation and characterization of decontamination and decommissioning solid waste expected from the Plutonium Finishing Plant

International Nuclear Information System (INIS)

Millar, J.S.; Pottmeyer, J.A.; Stratton, T.J.

1995-01-01

Purpose of the study was to estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the Hanford Plutonium Finishing Plant is decontaminated and decommissioned. (Building structure and soil are not covered.) Results indicate that ∼5,500 m 3 of solid waste is expected to result from the decontamination and decommissioning of the Pu Finishing Plant. The breakdown of the volumes and percentages of waste by category is 1% dangerous solid waste, 71% low-level waste, 21% transuranic waste, 7% transuranic mixed waste

Insight into economies of scale for waste packaging sorting plants

DEFF Research Database (Denmark)

Cimpan, Ciprian; Wenzel, Henrik; Maul, Anja

2015-01-01

of economies of scale and discussed complementary relations occurring between capacity size, technology level and operational practice. Processing costs (capital and operational expenditure) per unit waste input were found to decrease from above 100 € for small plants with a basic technology level to 60......This contribution presents the results of a techno-economic analysis performed for German Materials Recovery Facilities (MRFs) which sort commingled lightweight packaging waste (consisting of plastics, metals, beverage cartons and other composite packaging). The study addressed the importance......-70 € for large plants employing advanced process flows. Typical operational practice, often riddled with inadequate process parameters was compared with planned or designed operation. The former was found to significantly influence plant efficiency and therefore possible revenue streams from the sale of output...

Life-cycle assessment of a Waste-to-Energy plant in central Norway: Current situation and effects of changes in waste fraction composition.

Science.gov (United States)

Lausselet, Carine; Cherubini, Francesco; Del Alamo Serrano, Gonzalo; Becidan, Michael; Strømman, Anders Hammer

2016-12-01

Waste-to-Energy (WtE) plants constitute one of the most common waste management options to deal with municipal solid waste. WtE plants have the dual objective to reduce the amount of waste sent to landfills and simultaneously to produce useful energy (heat and/or power). Energy from WtE is gaining steadily increasing importance in the energy mix of several countries. Norway is no exception, as energy recovered from waste currently represents the main energy source of the Norwegian district heating system. Life-cycle assessments (LCA) of WtE systems in a Norwegian context are quasi-nonexistent, and this study assesses the environmental performance of a WtE plant located in central Norway by combining detailed LCA methodology with primary data from plant operations. Mass transfer coefficients and leaching coefficients are used to trace emissions over the various life-cycle stages from waste logistics to final disposal of the ashes. We consider different fractions of input waste (current waste mix, insertion of 10% car fluff, 5% clinical waste and 10% and 50% wood waste), and find a total contribution to Climate Change Impact Potential ranging from 265 to 637gCO 2 eq/kg of waste and 25 to 61gCO 2 eq/MJ of heat. The key drivers of the environmental performances of the WtE system being assessed are the carbon biogenic fraction and the lower heating value of the incoming waste, the direct emissions at the WtE plant, the leaching of the heavy metals at the landfill sites and to a lesser extent the use of consumables. We benchmark the environmental performances of our WtE systems against those of fossil energy systems, and we find better performance for the majority of environmental impact categories, including Climate Change Impact Potential, although some trade-offs exist (e.g. higher impacts on Human Toxicity Potential than natural gas, but lower than coal). Also, the insertion of challenging new waste fractions is demonstrated to be an option both to cope with the

Co-combustion of gasified contaminated waste wood in a coal fired power plant

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

This project demonstrates the technical and economical feasibility of the producing and cofiring of product gas from demolition waste wood. For this purpose LCV product gas is generated in an atmospheric circulating fluidized bed (CFB) gasification plant, cooled and cleaned and transported to the boiler of a 600 MWe pulverized coal fired power plant. Gas cooling and cleaning takes place in a waste heat boiler and a multi stage wet gas cleaning train. Steam raised in the waste heat boiler is exported to the power plant. On an annual basis 70,000 tons of steam coal are substituted by 150,000 tons of contaminated demolition waste wood (50,000 tons oil equivalent), resulting in a net CO2 emission reduction of 170,000 tons per year, while concurrently generating 205 GWh of electrical power. The wood gasification plant was built by NV EPZ (now incorporated in Essent Energi BV) for Amergas BV, now a 100% subsidiary of Essent Energie BV. The gasification plant is located at the Amer Power Station of NV EPZ Production (now Essent Generation) at Geertruidenberg, The Netherlands. Demonstrating several important design features in wood gasification, the plant started hot service in the Spring of 2000, with first gasification accomplished in the Summer of 2000 and is currently being optimized. (au)

Waste Isolation Pilot Plant in situ experimental program for HLW

International Nuclear Information System (INIS)

Molecke, M.A.

1977-01-01

The Waste Isolation Pilot Plant (WIPP) will be a facility to demonstrate the environmental and operational safety of storing radioactive wastes in a deep geologic bedded salt facility. The WIPP will be located in southeastern New Mexico, approximately 30 miles east of the city of Carlsbad. The major focus of the pilot plant operation involves ERDA defense related low and intermediate-level transuranic wastes. The scope of the project also specifically includes experimentation utilizing commercially generated high-level wastes, or alternatively, spent unreprocessed fuel elements. WIPP HLW experiments are being conducted in an inter-related laboratory, bench-scale, and in situ mode. This presentation focuses on the planned in situ experiments which, depending on the availability of commercially reprocessed waste plus delays in the construction schedule of the WIPP, will begin in approximately 1985. Such experiments are necessary to validate preceding laboratory results and to provide actual, total conditions of geologic storage which cannot be adequately simulated. One set of planned experiments involves emplacing bare HLW fragments into direct contact with the bedded salt environment. A second set utilizes full-size canisters of waste emplaced in the salt in the same manner as planned for a future HLW repository. The bare waste experiments will study in an accelerated manner waste-salt bed-brine interactions including matrix integrity/degradation, brine leaching, system chemistry, and potential radionuclide migration through the salt bed. Utilization of full-size canisters of HLW in situ permits us to demonstrate operational effectiveness and safety. Experiments will evaluate corrosion and compatibility interactions between the waste matrix, canister and overpack materials, getter materials, stored energy, waste buoyancy, etc. Using full size canisters also allows us to demonstrate engineered retrievability of wastes, if necessary, at the end of experimentation

Waste Isolation Pilot Plant safety analysis report

International Nuclear Information System (INIS)

1997-03-01

The United States Department of Energy (DOE) was authorized by Public Law 96-164 to provide a research and development facility for demonstrating the safe permanent disposal of transuranic (TRU) wastes from national defense activities and programs of the United States exempted from regulations by the US Nuclear Regulatory Commission (NRC). The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico near Carlsbad, was constructed to determine the efficacy of an underground repository for disposal of TRU wastes. In accordance with the 1981 and 1990 Records of Decision (ROD), the development of the WIPP was to proceed with a phased approach. Development of the WIPP began with a siting phase, during which several sites were evaluated and the present site selected based on extensive geotechnical research, supplemented by testing. The site and preliminary design validation phase (SPDV) followed the siting phase, during which two shafts were constructed, an underground testing area was excavated, and various geologic, hydrologic, and other geotechnical features were investigated. The construction phase followed the SPDV phase during which surface structures for receiving waste were built and underground excavations were completed for waste emplacement

PRIMING OF A LOW CAPACITY WASTE WATER TREATEMENT PLANT

Directory of Open Access Journals (Sweden)

Nicoleta Luminiţa Jurj

2012-12-01

Full Text Available In wastewater treatment plants, secondary biologic treatment is generally compulsory for the localities having less than 10,000 equivalent inhabitants, with a supplementary removal of nutrients if the area is a sensitive one. For the areas which are not suitable for centralized household used water collecting network individual treatment devices or collective low capacity devices are recommended. For certain settlements, for instance for the mountainous dispersed villages, or for detached individual households or farms the collective devices can not be an economic solution as involves high maintenance costs and exploiting problems due to long pipes for low flow rates. Priming is one of the starting up processes of a waste water treatment plant. This is not a very difficult process and requires no specialized staff. However, for helping the owners of a low capacity treatment plant, priming of ORM 5 type mechanical - biological equipment consisting in a tank with four compartments, designed for five equivalent inhabitants was studied inside the plant of Timisoara municipality. For the experimental tests waste water from the Timisoara city sewage network was used. This is mixed waste water resulted from faecal/domestic, industrial and rain water. The study comprised tests in unfavorable technological conditions. The conclusions of the monitoring process underline the need of control of the aeration process and the negative technological and consequently the negative economic effect of the less effective process control.

Waste Isolation Pilot Plant Biennial Environmental Compliance Report

Energy Technology Data Exchange (ETDEWEB)

Westinghouse TRU Solutions

2000-12-01

This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 1998, to March 31, 2000. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, and amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Area Office's (hereinafter the ''CAO'') compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. An issue was identified in the 1998 BECR relating to a potential cross-connection between the fire-water systems and the site domestic water system. While the CAO and its managing and operating contractor (hereinafter the ''MOC'') believe the site was always in compliance with cross-connection control requirements, hardware and procedural upgrades w ere implemented in March 1999 to strengthen its compliance posture. Further discussion of this issue is presented in section 30.2.2 herein. During this reporting period WIPP received two letters and a compliance order alleging violation of certain requirements outlined in section 9(a)(1) of the LWA. With the exception of one item, pending a final decision by the New Mexico Environment Department (NMED), all alleged violations have been resolved without the assessment of fines or penalties. Non-mixed TRU waste shipments began on March 26, 1999. Shipments continued through November 26, 1999, the effective date of the Waste Isolation Pilot Plant Hazardous Waste Facility Permit (NM4890139088-TSDF). No shipments regulated under the Hazardous Waste Facility Permit were received at WIPP during this BECR reporting period.

Waste Isolation Pilot Plant Biennial Environmental Compliance Report

International Nuclear Information System (INIS)

Westinghouse TRU Solutions

2000-01-01

This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 1998, to March 31, 2000. As required by the WIPP Land Withdrawal Act (LWA)(Public Law [Pub. L.] 102-579, and amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) Carlsbad Area Office's (hereinafter the ''CAO'') compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico. An issue was identified in the 1998 BECR relating to a potential cross-connection between the fire-water systems and the site domestic water system. While the CAO and its managing and operating contractor (hereinafter the ''MOC'') believe the site was always in compliance with cross-connection control requirements, hardware and procedural upgrades w ere implemented in March 1999 to strengthen its compliance posture. Further discussion of this issue is presented in section 30.2.2 herein. During this reporting period WIPP received two letters and a compliance order alleging violation of certain requirements outlined in section 9(a)(1) of the LWA. With the exception of one item, pending a final decision by the New Mexico Environment Department (NMED), all alleged violations have been resolved without the assessment of fines or penalties. Non-mixed TRU waste shipments began on March 26, 1999. Shipments continued through November 26, 1999, the effective date of the Waste Isolation Pilot Plant Hazardous Waste Facility Permit (NM4890139088-TSDF). No shipments regulated under the Hazardous Waste Facility Permit were received at WIPP during this BECR reporting period

Urban solid waste in the production of Lafoensia pacari seedlings

Directory of Open Access Journals (Sweden)

Alan H. M. de Abreu

Full Text Available ABSTRACT This study aimed to verify the potential of urban solid wastes as substrate for production of seedlings of Lafoensia pacari. Five treatments were tested, four with solid wastes and one standard substrate, namely: sewage sludge from Alegria Wastewater Treatment Plant (WTP; sewage sludge from Ilha do Governador WTP; sewage sludge from Sarapuí WTP; domestic garbage compost (Fertlurb; and a commercial substrate made of biostabilized pine bark (standard substrate. The wastes received 20% (in volume of shredded coconut fiber. At 105 days after sowing, the seedlings were evaluated for different quality parameters. Seedlings produced with Sarapuí WTP sewage sludge showed the best results in all the parameters, followed by seedlings produced with sewage sludge from Alegria and Ilha do Governador WTPs, which did not differ. Seedlings produced with domestic garbage compost showed satisfactory results, higher than the ones observed for seedlings produced with commercial substrate. The urban solid wastes with 20% of coconut fiber showed high potential and can be recommended for the composition of substrate in the production of Lafoensia pacari seedlings.

Transporting transuranic waste to the Waste Isolation Pilot Plant: Risk and cost perspectives

International Nuclear Information System (INIS)

Biwer, B. M.; Gilette, J. L.; Poch, L. A.; Suermann, J. F.

1999-01-01

The Waste Isolation Pilot Plant (WIPP) is an authorized US Department of Energy (DOE) research and development facility constructed near the city of Carlsbad in southeastern New Mexico. The facility is intended to demonstrate the safe disposal of transuranic (TRU) radioactive waste resulting from US defense activities. Under the WIPP Land Withdrawal Act of 1992 (LWA), federal lands surrounding the WIPP facility were withdrawn from all public use and the title of those lands was transferred to the Secretary of Energy. The DOE's TRU waste is stored, and in some cases is still being generated, at 10 large-quantity and 13 small-quantity sites across the US. After applicable certification requirements have been met, the TRU waste at these sites will be sent to the WIPP to initiate the disposal phase of the facility, which according to current planning is projected to last for approximately 35 years

Silicophosphate Sorbents, Based on Ore-Processing Plants' Waste in Kazakhstan

Science.gov (United States)

Kubekova, Sholpan N.; Kapralova, Viktoria I.; Telkov, Shamil A.

2016-01-01

The problem of ore-processing plants' waste and man-made mineral formations (MMF) disposal is very important for the Republic of Kazakhstan. The research of various ore types (gold, polymetallic, iron-bearing) MMF from a number of Kazakhstan's deposits using a complex physical and chemical methods showed, that the waste's main components are…

Mechanical and Morphological Properties of Waste Short Nylon Fibers and Nanoclay Reinforced NR/SBR Rubber Nanocomposites

Directory of Open Access Journals (Sweden)

Mohammad Andideh

2013-02-01

Full Text Available Natural rubber and styrene butadiene rubber (NR/SBR reinforced with short nylon fibers along with nanoclay (Cloisite 15A hybrid composites were prepared in an internal and a two roll-mill mixer by a three-step mixingprocess. The effects of fiber content at a constant loading of 3 wt% nanoclay were studied on the microstructure, mechanical and morphological properties of the prepared nanocomposites. The adhesion between the fiber and the rubber was enhanced by the addition of a dry bonding system consisting of resorcinol, hexamethylene tetramine and hydrated silica (HRH. The curing characteristics of the composites were determined and subsequently vulcanized at 150°C using a hot press. It was observed that the cure time and swelling index of the composites decreased while maximum torque, and cure rate increased with increasing of short fiber and nanoclay contents. Thestructure and fracture surface morphology of the nanocomposites were characterized using X-ray diffraction, scanning electron microscopy. X-ray diffraction results of nanocomposites indicated that the interlayer distance of silicate layers increased. The mechanical properties (tensile, tear strength, elongation-at-break and hardness ofnanocomposites containing virgin and waste fibers in the longitudinal direction are compared.

Power from waste. [Power plant at landfill site

Energy Technology Data Exchange (ETDEWEB)

Anon,

1991-01-01

Base Load Systems Ltd, a company in the United Kingdom, has just commissioned a power plant in Leicestershire which uses waste gases from a landfill site. The gases power two specially modified turbo charged engine and generator packages. The plant will use approximately 100 cu meters of landfill gas per hour and is expected to feed 1.5MW of electrical power into the supply network of East Midlands Electricity. Once the landfill site has been completely filled and capped with clay, it is estimated that the electrical power output will be 4 MW. At present, since their are no customers for heat in the vicinity, 100 KW of the electricity produced are used to run fans to dissipate the 2.5 MW of waste heat. Base load is also involved elsewhere in combined heat and power projects. (UK).

Methods for separating actinides from reprocessing and refabrication plant wastes

International Nuclear Information System (INIS)

Tedder, D.W.; Finney, B.C.; Blomeke, J.O.

1979-01-01

Chemical processing flowsheets have been developed to partition actinides from all actinide-bearing LWR fuel reprocessing and refabrication plant wastes. These wastes include high-activity-level liquids, scrap recovery liquors, HEPA filters and incinerator ashes, and chemical salt wastes such as sodium carbonate scrub solutions, detergent cleanup streams, and alkaline off-gas scrubber liquors. The separations processes that were adopted for this study are based on solvent extraction, cation exchange chromatography, and leaching with Ce 4+ -HNO 3 solution

Characterization of deposits and their influence on corrosion in waste incineration plants in Denmark

DEFF Research Database (Denmark)

Montgomery, Melanie; Larsen, OH

2001-01-01

A program has been initiated in Denmark to investigate the aggressive environment in various waste incineration plants. The results described are the preliminary results from one waste incineration plant. Deposits and corrosion products have been removed from various locations in the boiler...

Processing of ash and slag waste of heating plants by arc plasma to produce construction materials and nanomodifiers

Science.gov (United States)

Buyantuev, S. L.; Urkhanova, L. A.; Kondratenko, A. S.; Shishulkin, S. Yu; Lkhasaranov, S. A.; Khmelev, A. B.

2017-01-01

The resultsare presented of plasma processing slag and ash waste from coal combustion in heating plants. Melting mechanism of ashand slagraw material is considered by an electromagnetic technological reactor. The analysis was conducted of temperature and phase transformations of raw material when it is heated up to the melting point, and also determination of specific energy consumption by using a generalized model of the thermodynamic analysis of TERRA. The study of materials melting temperature conditions and plum of melt was carried with high-temperature thermal imaging method, followed by mapping and 3D-modeling of the temperature fields. The investigations to establish the principal possibilities of using slag waste of local coal as raw material for the production of mineral (ash and slag) fibers found that by chemical composition there are oxides in the following ranges: 45-65% SiO2; 10-25% Al2O3; 10-45% CaO; 5-10% MgO; other minerals (less than 5%). Thus, these technological wastes are principally suitable for melts to produce mineral wool by the plasma method. An analysis of the results shows the melting point of ash and slag waste - 1800-2000 °C. In this case the specific energy consumption of these processes keeps within the limits of 1.1-1.3 kW*h/kg. For comparison it should be noted that the unit cost of electricity in the known high-melting industrial installations 5-6 kW*h/kg. Upon melting ash and slag waste, which contains up to 2-5% of unburned carbon, carbon nanomaterials were discovered.in the form of ultrafine soot accumulating as a plaque on the water-cooled surfaces in the gas cleaning chamber. The process of formation of soot consists in sublimation-desublimation of part of carbon which is in ash and slag, and graphite electrode. Thus, upon melting of ash and slag in the electromagnetic reactor it is possible to obtain melt, and in the subsequent mineral high quality fiber, which satisfies the requirements of normative documents, and

Newly invented biobased materials from low-carbon, diverted waste fibers: research methods, testing, and full-scale application in a case study structure

Science.gov (United States)

Julee A Herdt; John Hunt; Kellen Schauermann

2016-01-01

This project demonstrates newly invented, biobased construction materials developed by applying lowcarbon, biomass waste sources through the Authors’ engineered fiber processes and technology. If manufactured and applied large-scale the project inventions can divert large volumes of cellulose waste into high-performance, low embodied energy, environmental construction...

Economic and ecologic considerations for bidding procedures and contracting for bio-waste fermentation plants

International Nuclear Information System (INIS)

Raussen, Thomas; Lootsma, Auke; Oldhafer, Nils

2013-01-01

The use of the energetic and mass potentials of biological wastes in an integrated fermentation and composting plant needs extensive conceptual and planning activities. The call for tenders for the construction of plants is an EU-wide open procedure. Public waste management organizations are interested to receive profitable solutions with reliable operation and minimized ecological impacts. The minimum requirements and technical aspects are defined by the public waste management organizations.

Application of Glass Fiber Waste Polypropylene Aggregate in Lightweight Concrete – thermal properties

Science.gov (United States)

Citek, D.; Rehacek, S.; Pavlik, Z.; Kolisko, J.; Dobias, D.; Pavlikova, M.

2018-03-01

Actual paper focus on thermal properties of a sustainable lightweight concrete incorporating high volume of waste polypropylene aggregate as partial substitution of natural aggregate. In presented experiments a glass fiber reinforced polypropylene (GFPP) which is a by-product of PP tubes production, partially substituted fine natural silica aggregate in 10, 20, 30, 40 and 50 mass %. Results were compared with a reference concrete mix without plastic waste in order to quantify the effect of GFPP use on concrete properties. Main material physical parameters were studied (bulk density, matrix density without air content, and particle size distribution). Especially a thermal transport and storage properties of GFPP were examined in dependence on compaction time. For the developed lightweight concrete, thermal properties were accessed using transient impulse technique, where the measurement was done in dependence on moisture content (from the fully water saturated state to dry state). It was found that the tested lightweight concrete should be prospective construction material possessing improved thermal insulation function and the reuse of waste plastics in concrete composition was beneficial both from the environmental and financial point of view.

WIPP [Waste Isolation Pilot Plant] test phase plan: Performance assessment

International Nuclear Information System (INIS)

1990-04-01

The U.S. Department of Energy (DOE) is responsible for managing the disposition of transuranic (TRU) wastes resulting from nuclear weapons production activities of the United States. These wastes are currently stored nationwide at several of the DOE's waste generating/storage sites. The goal is to eliminate interim waste storage and achieve environmentally and institutionally acceptable permanent disposal of these TRU wastes. The Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico is being considered as a disposal facility for these TRU wastes. This document describes the first of the following two major programs planned for the Test Phase of WIPP: Performance Assessment -- determination of the long-term performance of the WIPP disposal system in accordance with the requirements of the EPA Standard; and Operations Demonstration -- evaluation of the safety and effectiveness of the DOE TRU waste management system's ability to emplace design throughput quantities of TRU waste in the WIPP underground facility. 120 refs., 19 figs., 8 tabs

Modeling Hydrogen Generation Rates in the Hanford Waste Treatment and Immobilization Plant

Energy Technology Data Exchange (ETDEWEB)

Camaioni, Donald M.; Bryan, Samuel A.; Hallen, Richard T.; Sherwood, David J.; Stock, Leon M.

2004-03-29

This presentation describes a project in which Hanford Site and Environmental Management Science Program investigators addressed issues concerning hydrogen generation rates in the Hanford waste treatment and immobilization plant. The hydrogen generation rates of radioactive wastes must be estimated to provide for safe operations. While an existing model satisfactorily predicts rates for quiescent wastes in Hanford underground storage tanks, pretreatment operations will alter the conditions and chemical composition of these wastes. Review of the treatment process flowsheet identified specific issues requiring study to ascertain whether the model would provide conservative values for waste streams in the plant. These include effects of adding hydroxide ion, alpha radiolysis, saturation with air (oxygen) from pulse-jet mixing, treatment with potassium permanganate, organic compounds from degraded ion exchange resins and addition of glass-former chemicals. The effects were systematically investigated through literature review, technical analyses and experimental work.

Defense waste processing facility project at the Savannah River Plant

International Nuclear Information System (INIS)

Baxter, R.G.; Maher, R.; Mellen, J.B.; Shafranek, L.F.; Stevens, W.R. III.

1984-01-01

The Du Pont Company is building for the Department of Energy a facility to vitrify high-level waste at the Savannah River Plant near Aiken, South Carolina. The Defense Waste Processing Facility (DWPF) will solidify existing and future radioactive wastes produced by defense activities at the site. At the present time engineering and design are 45% complete, the site has been cleared, and startup is expected in 1989. This paper will describe project status as well as features of the design. 9 figures

Radioactive waste management at EDF plants: General overview and perspectives

International Nuclear Information System (INIS)

Debes, M.; Bordier, M.

2001-01-01

During the last fifteen years a significant decrease in solid radioactive waste generated by nuclear power plants of Electricite de France (EDF) has taken place. Technology used by EDF is described, with emphasis on innovative technologies. Experience and lessons learned are described showing how EDF has responded to meet increasingly stringent regulations for radioactive waste management. (author)

Chemical mode control in nuclear power plant decommissioning during operation of technologies in individual radioactive waste processing plants

International Nuclear Information System (INIS)

Horvath, J.; Dugovic, L.

1999-01-01

Sewage treatment of nuclear power plant decommissioning is performed by system of sewage concentration in evaporator with formation of condensed rest, it means radioactive waste concentrate and breeding steam. During sewage treatment plant operation department of chemical mode performs chemical and radiochemical analysis of sewage set for treatment, chemical and radiochemical analysis of breeding steam condensate which is after final cleaning on ionization filter and fulfilling the limiting conditions released to environment; chemical and radiochemical analysis of heating steam condensate which is also after fulfilling the limiting conditions released to environment. Condensed radioactive concentrate is stored in stainless tanks and later converted into easy transportable and chemically stable matrix from the long term storage point of view in republic storage Mochovce. The article also refer to bituminous plant, vitrification plant, swimming pool decontamination plant of long term storage and operation of waste processing plant Bohunice

The thermoelectric generators use for waste heat utilization from cement plant

Directory of Open Access Journals (Sweden)

Sztekler Karol

2017-01-01

Production often entails the formation of by-product which is waste heat. One of the equipment processing heat into electricity is a thermoelectric generator. Its operation is based on the principle of thermoelectric phenomenon, which is known as a Seebeck phenomenon. The simplicity of thermoelectric phenomena allows its use in various industries, in which the main waste product is in the form of heat with the temperature of several hundred degrees. The study analyses the possibility of the thermoelectric systems use for the waste heat utilization resulting in the cement production at the cement plant. The location and design of the thermoelectric system that could be implemented in cement plant is chosen. The analysis has been prepared in the IPSEpro software.

Potential for Producing Biogas from Agricultural Waste in Rural Plants in Poland

Directory of Open Access Journals (Sweden)

Magdalena Muradin

2014-08-01

Full Text Available This article is an overview of the current situation as well as future prospects for biogas production in rural plants in Poland. Our research has focused on the management of agricultural waste. While Poland’s agriculture and its local food industry have substantial potential, many barriers persist to the development not only of biogas plants but also in every other renewable source of energy. The main obstacles have to do with politically motivated economic factors. Our interest has been in larger plants having sufficient capacities to produce in excess of 500 kW of electricity. The paper also presents a case study of a biogas plant supply by organic, agrifood waste mixed with silage.

Improved liquid waste processing system of PWR plant

International Nuclear Information System (INIS)

Suehiro, Kazuyasu

1977-01-01

Mitsubishi Heavy Industries, Ltd. has engaged in the improvement and enhancement of waste-processing facilities for PWR power stations, and recently established the improved processing system. With this system, it becomes possible to contain radioactive waste gas semi-permanently within plants and to recycle waste liquid after the treatment, thus to make the release of radioactive wastes practically zero. The improved system has the following features, namely the recycling system is adopted, drain is separated and each separated drain is treated by specialized process, the reboiler type evaporator and the reverse osmosis equipment are used, and the leakless construction is adopted for the equipments. The radioactive liquid wastes in PWR power stations are classified into coolant drain, drain from general equipments, chemical drain and cleaning water. The outline of the improved processing system and the newly developed equipments such as the reboiler type evaporator and the reverse osmosis equipment are explained. With the evaporator, the concentration rate of waste liquid can be raised to about three times, and foaming waste can be treated efficiently. The decontamination performance is excellent. The reverse osmosis treatment is stable and reliable method, and is useful for the treatment of cleaning water. It is also effective for concentrating treatment. The unmanned automatic operation is possible. (Kako, I.)

Waste Isolation Pilot Plant, Land Management Plan

International Nuclear Information System (INIS)

1993-01-01

To reflect the requirement of section 4 of the Wastes Isolation Pilot Plant Land Withdrawal Act (the Act) (Public Law 102-579), this land management plan has been written for the withdrawal area consistent with the Federal Land Policy and Management Act of 1976. The objective of this document, per the Act, is to describe the plan for the use of the withdrawn land until the end of the decommissioning phase. The plan identifies resource values within the withdrawal area and promotes the concept of multiple-use management. The plan also provides opportunity for participation in the land use planning process by the public and local, State, and Federal agencies. Chapter 1, Introduction, provides the reader with the purpose of this land management plan as well as an overview of the Waste Isolation Pilot Plant. Chapter 2, Affected Environment, is a brief description of the existing resources within the withdrawal area. Chapter 3, Management Objectives and Planned Actions, describes the land management objectives and actions taken to accomplish these objectives

Waste Isolation Pilot Plant, Land Management Plan

Energy Technology Data Exchange (ETDEWEB)

1993-12-01

To reflect the requirement of section 4 of the Wastes Isolation Pilot Plant Land Withdrawal Act (the Act) (Public Law 102-579), this land management plan has been written for the withdrawal area consistent with the Federal Land Policy and Management Act of 1976. The objective of this document, per the Act, is to describe the plan for the use of the withdrawn land until the end of the decommissioning phase. The plan identifies resource values within the withdrawal area and promotes the concept of multiple-use management. The plan also provides opportunity for participation in the land use planning process by the public and local, State, and Federal agencies. Chapter 1, Introduction, provides the reader with the purpose of this land management plan as well as an overview of the Waste Isolation Pilot Plant. Chapter 2, Affected Environment, is a brief description of the existing resources within the withdrawal area. Chapter 3, Management Objectives and Planned Actions, describes the land management objectives and actions taken to accomplish these objectives.

Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

International Nuclear Information System (INIS)

1991-01-01

This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). DOE plans to conduct experiments in the WIPP during a Test Phase of approximately 5 years. These experiments will be conducted to reduce the uncertainties associated with the prediction of several processes (e.g., gas generation) that may influence repository performance. The results of the experiments will be used to assess the ability of the WIPP to meet regulatory requirements for the long-term protection of human health and the environment from the disposal of TRU wastes. 37 refs., 25 figs., 18 tabs

High-rate tensile behavior of steel fiber-reinforced concrete for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Kim, Jung Jin; Park, Gi-Joon [Department of Civil and Environmental Engineering, Sejong University, 98 Gunja-Dong, Gwangjin-Gu, Seoul 143-747 (Korea, Republic of); Kim, Dong Joo, E-mail: djkim75@sejong.ac.kr [Department of Civil and Environmental Engineering, Sejong University, 98 Gunja-Dong, Gwangjin-Gu, Seoul 143-747 (Korea, Republic of); Moon, Jae Heum; Lee, Jang Hwa [Korea Institute of Construction Technology, 2311 Daewha-Dong, Ilsan-Gu, Goyang-Si, Gyeonggi-Do 411-712 (Korea, Republic of)

2014-01-15

Highlights: • The final goal is to develop a fiber reinforced concrete for containment buildings. • High rate tensile behavior of FRC was investigated. • Strain energy frame impact machine was used for tensile impact tests. • Different rate sensitivity of FRC was found according to the type fiber. • Adding more fibers by increasing S/a is positive for higher impact resistance of FRC. -- Abstract: The direct tensile behavior of fiber-reinforced concrete (FRC) at high strain rates were investigated for their potential to enhance the resistance of the containment building of nuclear power plants (NPPs) against aircraft impact. Two types of deformed steel, hooked (H) and twisted (T) fibers were employed. To improve the tensile resistance of FRCs even at higher rates by adding more fibers, the mixture of concrete was modified by either increasing the sand-to-coarse aggregate ratio or decreasing the maximum size of coarse aggregate. All FRC specimens produced two to six times greater tensile strength and one to five times higher toughness at high strain rates (4–53 s{sup −1}) than those at a static rate (0.000167 s{sup −1}). T-fiber generally produced higher tensile strength and toughness than H-fiber at both static and high rates. Although both fibers showed favorable rate sensitivity, T-fiber produced much greater enhancement, at higher strain rates, in tensile strength and slightly lower enhancement in toughness than H-fiber. As the maximum size of coarse aggregate decreased from 19 to 5 mm, the tensile strength and toughness of FRCs with T-fibers noticeably increased at both static and high strain rates.

Problems of Waste Management at Poultry Plants and Ways to Address Them

Science.gov (United States)

Lazareva, L. P.; Kostryakova, O. N.

2017-11-01

The paper analyzes scientific literature on manure recycling and systems of waste management at two poultry plants that use different technologies of poultry housing and manure disposal and calculates the volumes of waste generation for two plants. The authors suggest an economically and ecologically efficient manure utilization technology, consider the feasibility of replacing traditional fuel with the one produced by manure recycling and calculate expected profits and the payback time of equipment.

The validation of waste assay systems during active test at Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Tamura, Takayuki; Miura, Yasushi; Iwamoto, Tomonori

2007-01-01

In order to implement accurate material accountancy at Rokkasho Reprocessing Plant (RRP) as a large scale reprocessing plant, it is necessary to introduce accurate measurement systems not only for mainstream material, but also appropriate measurement systems for solid waste materials. In this sense, the generated wastes by the active test operation have been measured with the Non-Destructive Assay Systems, such as Rokkasho Hulls Measurement System (RHMS) and Waste Crate Assay System (WCAS) for accountancy. This paper describes the experience of the NDA operation and the evaluation results for accountancy. (author)

The recovery of waste and off-gas in Large Combustion Plants subject to IPPC National Permit in Italy.

Science.gov (United States)

Di Marco, Giuseppe; Manuzzi, Raffaella

2018-03-01

The recovery of off-gas, waste, and biomass in Large Combustion Plants for energy production gives the opportunity to recycle waste and by-products and to recover materials produced in agricultural and industrial activities. The paper illustrates the Italian situation regarding the production of energy from off-gas, biomass, and waste in Large Combustion Plants subject to Integrated Pollution Prevention and Control (IPPC) National Permit. Moreover, it focuses on the 4 Italian Large Combustion Plants producing energy from biomass and waste. For these ones it illustrates the specific issues related to and provides a description of the solutions adopted in the 4 Italian plants. Given that air emission performance is the most relevant aspect of this kind of plants, the paper specifically focuses and reports results about this subject. In particular, in Italy among 113 LCPs subject to IPPC National Permit we have found that 4 plants use as fuel waste (i.e. solid or liquid biomasses and Solid Recovered Fuels), or a mixture of waste and traditional fuels (co-combustion of Solid Recovered Fuels and coal), and that 11 plants use as fuel off-gases listed in Annex X (i.e. Refinery Fuel Gas, Syngas, and gases produced in iron and steel industries). Moreover, there are 2 IPPC chemical plants that recovery energy from different off-gases not listed in Annex X. Regarding the 4 LCPs that produce energy from waste combustion or co-combustion, we find that they take into account all the specific issues related to this kind of plants (i.e. detailed waste characterization, waste acceptance procedures, waste handling and storage, waste pretreatment and emissions to air), and adopt solutions that are best available techniques to prevent pollution. Moreover for one of these plants, the only one for which we have a significant set of monitoring data because it obtained the IPPC National Permit in 2008, we find that energy efficiency and air emissions of the principal pollutants are in

Waste Isolation Pilot Plant Biennial Environmental Compliance Report

Energy Technology Data Exchange (ETDEWEB)

Washington Regulatory and Environmental Services (WRES)

2004-10-25

This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2002, to March 31, 2004. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico.

Development of low level radioactive waste incineration plant

International Nuclear Information System (INIS)

Shaharum bin Ramli; Azmir bin Hanafiah

1994-01-01

A laboratory scale liquid waste incineration plant has been constructed. Preliminary tests were conducted by burning kerosene as the waste. The temperature reached 1200 deg.C. The exhaust gas was analysed for CO and CO sub 2 content. The hydrocarbon content was not measured without the proper analyser. Thus, parameters such as the optimum air:kerosene ratio and the maximum kerosene injection rate could not be determined. Complete tests will be carried out with the newly received hydrocarbon, NO sub x, CO, CO sub 2 and O sub 2 gas analyser

Waste Isolation Pilot Plant Biennial Environmental Compliance Report

International Nuclear Information System (INIS)

2004-01-01

This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2002, to March 31, 2004. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico.

Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

International Nuclear Information System (INIS)

Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

1985-07-01

This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m 3 /MTU for no treatment to as low as 0.02 m 3 /MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs

Preliminary analysis of treatment strategies for transuranic wastes from reprocessing plants

Energy Technology Data Exchange (ETDEWEB)

Ross, W.A.; Schneider, K.J.; Swanson, J.L.; Yasutake, K.M.; Allen, R.P.

1985-07-01

This document provides a comparison of six treatment options for transuranic wastes (TRUW) resulting from the reprocessing of commercial spent fuel. Projected transuranic waste streams from the Barnwell Nuclear Fuel Plant (BNFP), the reference fuel reprocessing plant in this report, were grouped into the five categories of hulls and hardware, failed equipment, filters, fluorinator solids, and general process trash (GPT) and sample and analytical cell (SAC) wastes. Six potential treatment options were selected for the five categories of waste. These options represent six basic treatment objectives: (1) no treatment, (2) minimum treatment (compaction), (3) minimum number of processes and products (cementing or grouting), (4) maximum volume reduction without decontamination (melting, incinerating, hot pressing), (5) maximum volume reduction with decontamination (decontamination, treatment of residues), and (6) noncombustible waste forms (melting, incinerating, cementing). Schemes for treatment of each waste type were selected and developed for each treatment option and each type of waste. From these schemes, transuranic waste volumes were found to vary from 1 m/sup 3//MTU for no treatment to as low as 0.02 m/sup 3//MTU. Based on conceptual design requirements, life-cycle costs were estimated for treatment plus on-site storage, transportation, and disposal of both high-level and transuranic wastes (and incremental low-level wastes) from 70,000 MTU. The study concludes that extensive treatment is warranted from both cost and waste form characteristics considerations, and that the characteristics of most of the processing systems used are acceptable. The study recommends that additional combinations of treatment methods or strategies be evaluated and that in the interim, melting, incineration, and cementing be further developed for commercial TRUW. 45 refs., 9 figs., 32 tabs.

Long-term safety of the maintenance and decommissioning waste of the encapsulation plant

International Nuclear Information System (INIS)

Nummi, O.; Kylloenen, J.; Eurajoki, T.

2012-12-01

This report, Long-term safety of the maintenance and decommissioning waste of the encapsulation plant, presents the disposal concept for the low and intermediate level waste (L/ILW) that is generated during the operation and decommissioning of the encapsulation plant, and assesses the long-term safety of the disposal of the waste. Radioactive waste originates from the spent nuclear fuel transferred and dried in the encapsulation plant. Radioactive waste accumulates also in the maintenance of the components and systems of the encapsulation plant. The waste is collected, exempted from control if possible and treated for final disposal if necessary. The waste is disposed of in the L/ILW hall which is currently planned to be located at a depth of -180 meters along the access tunnel to the repository for spent fuel. The main engineered barrier in the L/ILW hall is a concrete basin that encases the dried liquid waste. The safety concept of L/ILW disposal is based on the slow release of radioactivity from the L/ILW hall and its limited transport through the bedrock into biosphere. The release and transport of the radioactivity is described by the assessment scenarios, which include expected evolution and unlikely events affecting the long-term safety. The scenarios act as guidelines according to which the conceptual and mathematical models are formed. The long-term safety of the L/ILW hall is assessed using deterministic and probabilistic modeling. Special issues such as human intrusion and radiation effects on other biota are also assessed. The most significant contributor to the dose rates is the short-lived radionuclide 90 Sr followed by long-lived nuclides 129 I and 108 mAg. The annual doses to the public, and release rates of radioactive substances stay below the regulatory constraints in all analyzed scenarios. (orig.)

Waste Isolation Pilot Plant Site Environmental Report for calendar year 1989

International Nuclear Information System (INIS)

1989-01-01

This is the 1989 Site Environmental Report (SER) for the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico. The WIPP is a government owned and contractor-operated facility. The WIPP project is operated by Westinghouse Electric Corporation for the US Department of Energy (DOE). The mission of the WIPP is to provide a research and development facility to demonstrate the safe disposal of transuranic (TRU) waste generated by the defense activities of the US Government. This report provides a comprehensive description of environmental activities at the WIPP during calendar year 1989. The WIPP facility will not receive waste until all concerns affecting opening the WIPP are addressed to the satisfaction of the Secretary of Energy. Therefore, this report describes the status of the preoperational activities of the Radiological Environmental Surveillance (RES) program, which are outlined in the Radiological Baseline Program for the Waste Isolation Pilot Plant (WTSD-TME-057). 72 refs., 13 figs., 20 tabs

Steam generators and waste heat boilers for process and plant engineers

CERN Document Server

Ganapathy, V

2014-01-01

Incorporates Worked-Out Real-World ProblemsSteam Generators and Waste Heat Boilers: For Process and Plant Engineers focuses on the thermal design and performance aspects of steam generators, HRSGs and fire tube, water tube waste heat boilers including air heaters, and condensing economizers. Over 120 real-life problems are fully worked out which will help plant engineers in evaluating new boilers or making modifications to existing boiler components without assistance from boiler suppliers. The book examines recent trends and developments in boiler design and technology and presents novel idea

Hanford Waste Simulants Created to Support the Research and Development on the River Protection Project - Waste Treatment Plant

Energy Technology Data Exchange (ETDEWEB)

Eibling, R.E.

2001-07-26

The development of nonradioactive waste simulants to support the River Protection Project - Waste Treatment Plant bench and pilot-scale testing is crucial to the design of the facility. The report documents the simulants development to support the SRTC programs and the strategies used to produce the simulants.

Selected problems of minimization and management of radioactive wastes from nuclear power plant decommissioning. Part 2

International Nuclear Information System (INIS)

Kyrs, M.; Moravec, A.

1988-06-01

The processing prior to storage of radioactive wastes produced in nuclear power plant decommissioning is described as are the types of containers employed for waste transport and/or disposal. Data are summarized on exposure of personnel to radioactivity resulting from nuclear power plant decommissioning activities, and accessible data are collected on the costs of nuclear power plant decommissioning and of waste management. Potential directions of research in this field under Czechoslovak conditions are specified. (author)

Separation efficiency of two waste polymer fibers for oily water treatment

Directory of Open Access Journals (Sweden)

Sokolović Dunja S.

2016-01-01

Full Text Available This work is concerned with the efficiency of two different waste polymeric materials as the filter media in a laboratory-scale bed coalescer in the horizontal fluid flow mode, operating in a steady-state regime. The applied materials are: waste polyethylene terephthalate from textile industry, BA1 and waste polypropylene from carpet industry, PP. Using these compressible fiber polymeric materials, high bed porosity (up to 98% could be obtained. The investigation was carried out over a wide range of working conditions. Bed permeability was varied in the range from 0.18•10-9 to 5.389•10-9 m2. Operating fluid velocity was varied from 19 to 80 m/h, until the critical velocity was reached. Different oily wastewaters were used in the experiments. Oily wastewater is defined as the oil-inwater emulsion model prepared using mineral oils of different physico-chemical characteristics: crude oil (A from Vojvodina region, two vacuum distillation fractions (A1, A4, and blended petroleum product with a high paraffinic content (P1. Both applied polymeric materials, BA1 and PP, showed high separation efficiency for treatment of all investigated oily wastewater. However, the BA1 material showed higher efficiency in a wider range of bed permeability and physico-chemical characteristics of oil. [Projekat Ministarstva nauke Republike Srbije, br. 172022

Liquid and solid rad waste treatment in advanced nuclear power plants. Application to the SBWR design

International Nuclear Information System (INIS)

Tielas Reina, M.; Asuar Alonso, O.

1994-01-01

Rad waste treatment requirements for the new generation of American advanced passive and evolutionary power plants are listed in the URD (Utility Requirements Document) of the EPRI (Electrical Power Research Institute). These requirements focus on: - Minimization of shipped solid wastes - Minimization of liquid effluents - Simplification of design and operation, with emphasis not only on waste treatment system design but also on general plant design and operation These objectives are aimed at: - Reducing and segregating wastes at source - Minimizing chemical contamination of these wastes System design simplification is completed by providing free space in the building for the use of mobile plants, either for special services not considered in the basic design or to accommodate future technical advances. (Author)

U.S. Department of Energy Implementation of Chemical Evaluation Requirements for Transuranic Waste Disposal at the Waste Isolation Pilot Plant

Energy Technology Data Exchange (ETDEWEB)

Moon, Alison [USDOE Office of Environmental Management (EM), Washington, DC (United States); Barkley, Michelle [USDOE Office of Environmental Management (EM), Washington, DC (United States); Poppiti, James [USDOE Office of Environmental Management (EM), Washington, DC (United States)

2017-07-01

This report summarizes new controls designed to ensure that transuranic waste disposed at the Waste Isolation Pilot Plant (WIPP) does not contain incompatible chemicals. These new controls include a Chemical Compatibility Evaluation, an evaluation of oxidizing chemicals, and a waste container assessment to ensure that waste is safe for disposal. These controls are included in the Chapter 18 of the Documented Safety Analysis for WIPP (1).

U.S. Department of Energy Implementation of Chemical Evaluation Requirements for Transuranic Waste Disposal at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Moon, Alison; Barkley, Michelle; Poppiti, James

2017-01-01

This report summarizes new controls designed to ensure that transuranic waste disposed at the Waste Isolation Pilot Plant (WIPP) does not contain incompatible chemicals. These new controls include a Chemical Compatibility Evaluation, an evaluation of oxidizing chemicals, and a waste container assessment to ensure that waste is safe for disposal. These controls are included in the Chapter 18 of the Documented Safety Analysis for WIPP (1).

Characterization of natural fiber from agricultural-industrial residues

International Nuclear Information System (INIS)

Prado, Karen S.; Spinace, Marcia A.S.

2011-01-01

Natural fibers show great potential for application in polymer composites. However, instead of the production of inputs for this purpose, an alternative that can also minimize solid waste generation is the use of agro-industrial waste for this purpose, such as waste-fiber textiles, rice husks residues and pineapple crowns. In this work the characterization of these three residues and evaluate their properties in order to direct the application of polymer composites. Was analyzed the moisture, density, scanning electron microscopy, X-ray diffraction and thermogravimetric analysis of the fibers. The results show that the use of these wastes is feasible both from an environmental standpoint and because its properties suitable for this application. (author)

Use of fixation techniques in processing radioactive wastes from nuclear power plants in Czechoslovakia

International Nuclear Information System (INIS)

Seliga, M.

1977-01-01

The current state of radioactive waste disposal from the Bohunice nuclear power plant is described. The method of vacuum cementation was chosen for solidifying liquid radioactive wastes. This method makes it possible to obtain a product whose properties, namely strength, leachability, and radiation stability allow for the production of blocks without packing material. Also solved was the fixation of liquid radioactive waste using bituminization based on mixing liquid radioactive waste with aqueous bitumen emulsion in a film evaporator in which the mixture of liquid radioactive wastes and bitumen emulsion evaporate producing solid bitumen. The parameters are given of the cementation and bituminization lines which are designed for use in nuclear power plants with WWER type reactors. (J.B.)

No-migration variance petition for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Duff, M.; Carnes, R.; Hart, J.; Hansen, R.

1991-01-01

The US Department of Energy (DOE) is petitioning the US Environmental Protection Agency (EPA) to allow the emplacement of hazardous wastes subject to the Resource Conservation and Recovery Act (RCRA) land disposal restrictions in the Waste Isolation Pilot Plant (WIPP). The basis of the petition is that there will be no migration of hazardous constituents from the repository for as long as the wastes remain hazardous. The EPA regulations in 40 CFR Section 268.6 identify specific criteria that must be addressed in making a demonstration of no migration. EPA's approval of this petition will allow the WIPP facility to accept wastes otherwise prohibited or restricted from land disposal. 5 refs

TRU [transuranic] waste certification compliance requirements for acceptance of newly generated contact-handled wastes to be shipped to the Waste Isolation Pilot Plant: Revision 2

International Nuclear Information System (INIS)

1989-01-01

Compliance requirements are presented for certifying that unclassified, newly generated (NG), contact-handled (CH) transuranic (TRU) solid wastes from defense programs meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). Where appropriate, transportation and interim storage requirements are incorporated; however, interim storage sites may have additional requirements consistent with these requirements. All applicable Department of Energy (DOE) orders must continue to be met. The compliance requirements for stored or buried waste are not addressed in this document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 10 refs., 1 fig

Removal of Pb(II) from wastewater using Al2O3-NaA zeolite composite hollow fiber membranes synthesized from solid waste coal fly ash.

Science.gov (United States)

Zhu, Li; Ji, Jiayou; Wang, Shulin; Xu, Chenxi; Yang, Kun; Xu, Man

2018-09-01

Al 2 O 3 -NaA zeolite composite hollow fiber membranes were successfully fabricated via hydrothermal synthesis by using industrial solid waste coal fly ash and porous Al 2 O 3 hollow fiber supports. The as-synthesized Al 2 O 3 -NaA zeolite composite hollow fiber membranes were then characterized by scanning electron microscopy (SEM) and X-ray diffraction (XRD). The hollow fiber membranes were used to remove lead ions (Pb(II), 50 mg L -1 ) from synthetic wastewater with a removal efficiency of 99.9% at 0.1 MPa after 12 h of filtration. This study showed that the Al 2 O 3 -NaA zeolite composite hollow fiber membranes (the pore size of the membrane was about 0.41 nm in diameter) synthesized from coal fly ash could be efficiently used for treating low concentration Pb(II) wastewater. It recycled solid waste coal fly ash not only to solve its environment problems, but also can produce high-value Al 2 O 3 -NaA zeolite composite hollow fiber membranes for separation application in treating wastewater containing Pb(II). Copyright © 2018 Elsevier Ltd. All rights reserved.

Air-Cured Fiber-Cement Composite Mixtures with Different Types of Cellulose Fibers

Directory of Open Access Journals (Sweden)

Ali Murat Soydan

2018-01-01

Full Text Available This present study was carried out to check the feasibility of different cellulose fibers obtained from cropped virgin cellulose, blenched eucalyptus, and araucaria pulps through different new environmentally friendly curing processes for fiber-cement production. The aim is to introduce the different sources of cellulose fibers with lower cost to produce the “fiber-cement without autoclave” (FCWA. The slurries used in the experiments contain approximately 8% wt. of cellulose. The influence of the waste marble powder addition to the cement mixture was also studied. The physical and mechanical properties of the products which were prepared with this method under different curing conditions were investigated. The mechanical properties of eucalyptus cellulose appear to offer the best combination, especially after longer air-cure cycles. The results showed that the production of FCWA is very economical by using waste marble powders. And moreover, two new types of cellulose fibers (eucalyptus and araucaria celluloses; EuC and ArC, resp., which provide a better density and packing in the fiber-cement leading to better modulus of rupture (MOR and modulus of elasticity (MOE values as virgin cellulose (ViC, are very usable for production of the fiber-cement in industrial scale.

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)

Analytical technology in support of the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Villareal, R.

1994-01-01

The need for long-term disposal of defense-related transuranic (TRU) wastes became apparent as the DOE recognized the environmental consequences of maintaining waste storage facilities designed for short or interim storage periods, not long-term storage. In 1979, Congress authorized the Waste Isolation Pilot Plant (WIPP), a research and development facility and full-scale pilot plant, to demonstrate the safe management, storage, and disposal of TRU wastes. Environmental Protection Agency (EPA) regulations governing disposal of TRU wastes in 40 CFR 191 require that TRU waste disposal systems be designed to limit migration of radionuclides to the accessible environment for 10,000 years based on performance assessment results. The actinide source-term waste test program (STTP) is an experiment designed to quantitatively measure the time-dependent concentrations of plutonium, uranium, neptunium, thorium, and americium in TRU wastes immersed in brines that simulate the chemistry that may occur in WIPP disposal rooms, partially or completely contacted with brines. The total concentration of each actinide in brine is the sum of its dissolved and colloidally suspended components, as determined by variables including pcH, oxidation-reduction potential (Eh), chelating and complexing agents, sorption capacity, and colloidal suspension capabilities. To determine the effect of influencing variables on the concentration of actinides in WIPP brines, several TRU waste types will be characterized and loaded into specially designed noncorrosive test containers filled with brine containing additives to enhance the action of each influencing variable. The test container brine and headspace gases will be analyzed

Radiation protection at UKAEA's solid waste plant at Harwell

International Nuclear Information System (INIS)

Gallacher, G.; Tierney, T.

2006-01-01

The paper provides an overview of the solid waste plant at Harwell ( United Kingdom)Examples of waste streams, processes and the supporting health physics measures have been briefly described. It is clear that all waste operations involve close team work between staff from U.K.A.E.A. (United Kingdom Atomic Energy Authority) operations and health physics staff from both U.K.A.E.A. and RWE NUKEM (RWE NUKEM is one of the health physics support contractors). Work must be planned carefully, and radiological conditions monitored to ensure that the job is progressing smoothly and workplace exposure remains as low as reasonably practicable. (authors)

High level waste vitrification at the SRP [Savannah River Plant] (DWPF [Defense Waste Processing Facility] summary)

International Nuclear Information System (INIS)

Weisman, A.F.; Knight, J.R.; McIntosh, D.L.; Papouchado, L.M.

1988-01-01

The Savannah River Plant has been operating a nuclear fuel cycle since the early 1950's. Fuel and target elements are fabricated and irradiated to produce nuclear materials. After removal from the reactors, the fuel elements are processed to extract the products, and waste is stored. During the thirty years of operation including evaporation, about 30 million gallons of high level radioactive waste has accumulated. The Defense Waste Processing Facility (DWPF) under construction at Savannah River will process this waste into a borosilicate glass for long-term geologic disposal. The construction of the DWPF is about 70% complete; this paper will describe the status of the project, including design demonstrations, with an emphasis on the melter system. 9 figs

Progress in long-lived radioactive waste management and disposal at the waste isolation pilot plant

International Nuclear Information System (INIS)

Triay, I.R.; Matthews, M.L.; Eriksson, L.G.

2001-01-01

The Salado Formation is buried more than 350 m beneath the sands and cacti of the Chihuahuan Desert and hosts the Waste Isolation Pilot Plant (WIPP) deep geological repository at a depth of approximately 650 m. Since the WIPP repository is at least 10 years ahead of any other repository development for long-lived radioactive waste, other radioactive waste management organizations and institutions could benefit both scientifically and politically from sharing the lessons learned at WIPP. Benefits would include using existing expertise and facilities to cost-effectively address and solve program-specific issues and to train staff. The characteristics of the WIPP repository and infrastructure are described in this paper. (author)

Progress in long-lived radioactive waste management and disposal at the waste isolation pilot plant

Energy Technology Data Exchange (ETDEWEB)

Triay, I R; Matthews, M L [U.S. Dept. of Energy Carlsbad Field Office, New Mexico (United States); Eriksson, L G [GRAM, Inc., Albuquerque, NM (United States)

2001-07-01

The Salado Formation is buried more than 350 m beneath the sands and cacti of the Chihuahuan Desert and hosts the Waste Isolation Pilot Plant (WIPP) deep geological repository at a depth of approximately 650 m. Since the WIPP repository is at least 10 years ahead of any other repository development for long-lived radioactive waste, other radioactive waste management organizations and institutions could benefit both scientifically and politically from sharing the lessons learned at WIPP. Benefits would include using existing expertise and facilities to cost-effectively address and solve program-specific issues and to train staff. The characteristics of the WIPP repository and infrastructure are described in this paper. (author)

Physical, chemical and mineralogical characterization of water treatment plant waste for use in soil-cement brick

International Nuclear Information System (INIS)

Pessin, L.R.; Destefani, A.Z.; Holanda, J.N.F.

2011-01-01

The water treatment plants (WTP) for human consumption generate huge amounts of waste in the form of sludge (sludge) that have been over the years mostly inadequately prepared in water resources and the environment. Moreover, traditional methods of disposal of waste water treatment plants commonly used are generally costly activities. An alternative method for disposal of this waste abundant is its incorporation in ceramic products. This work is focused on the physical-chemical and mineralogical composition of a sample of waste water treatment plants from the region of Campos dos Goytacazes-RJ to their use in the manufacture of soil-cement brick. Several characterization techniques were used including X-ray diffraction, X-ray fluorescence, scanning electron microscopy, picnometry, particle size analysis and plasticity. The experimental results indicate that the waste water treatment plants have the potential to be used in the manufacture of ecologic soil-cement bricks. (author)

Barium and sodium in sunflower plants cultivated in soil treated with wastes of drilling of oil well

Directory of Open Access Journals (Sweden)

Jésus Sampaio Junior

2015-11-01

Full Text Available ABSTRACTThis study aimed to evaluate the effects of the application of two types of oil drilling wastes on the development and absorption of barium (Ba and sodium (Na by sunflower plants. The waste materials were generated during the drilling of the 7-MGP-98D-BA oil well, located in the state of Bahia, Brazil. The treatments consisted of: Control – without Ba application, comprising only its natural levels in the soil; Corrected control – with fertilization and without wastes; and the Ba doses of 300, 3000 and 6000 mg kg-1, which were equivalent to the applications of 16.6, 165.9 and 331.8 Mg ha-1 of waste from the dryer, and 2.6, 25.7 and 51.3 Mg ha-1 of waste from the centrifugal. Plants cultivated using the first dose of dryer waste and the second dose of centrifugal waste showed growth and dry matter accumulation equal to those of plants under ideal conditions of cultivation (corrected control. The highest doses of dryer and centrifugal wastes affected the development of the plants. The absorption of Ba by sunflower plants was not affected by the increase in the doses. Na proved to be the most critical element present in the residues, interfering with sunflower development.

Waste Isolation Pilot Plant Strategic Plan

International Nuclear Information System (INIS)

1993-03-01

The purpose of the Waste Isolation Pilot Plant (WIPP) Strategic Plan is to provide decision makers, project participants, and the public with a high-level overview of the objectives, issues, and strategiesthat impact a decision on the suitability of WIPP as a permanent, safe disposal facility for transuranic (TRU) waste that has resulted from defense activities. This document is a component of an integrated planning process and is a key management tool that is coordinated and consistent with the Secretary's Disposal Decision Plan and the Environmental Restoration and Waste Management (EM) Five-Year Plan. This documentsupports other US Department of Energy (DOE) planning efforts, including the TRU Waste Program. The WIPP Strategic Plan addresses the WIPP Program Test Phase, Disposal Decision, Disposal Phase, and Decommissioning Phase (decontamination and decommissioning). It describes the actions and activities that the DOE will conduct to ensure that WIPP will comply with applicable, relevant, and appropriate requirements of the US Environmental Protection Agency (EPA), State of New Mexico, and other applicable federal and state regulations. It also includes the key assumptions under which the strategy was developed. A comprehensive discussion of the multitude of activities involved in the WIPP Program cannot be adequately presented in this document. The specific details of these activities are presented in other, more detailed WIPP planningdocuments

Improved electrical efficiency and bottom ash quality on waste combustion plants. Final report

Energy Technology Data Exchange (ETDEWEB)

Jensen, Peter A.; Nesterov, I.; Boejer, M.; Hyks, J.; Astrup, T.; Kloeft, H.; Dam-Johansen, K.; Lundtorp, K.; Hedegaard Madsen, O.; Frandsen, F. (Technical Univ. of Denmark, Kgs. Lyngby (Denmark)); Mogensen, Erhardt (Babcock and Wilcox Voelund A/S, Glostrup (Denmark))

2010-07-01

Investigations making it possible to evaluate and further develop concepts to improve electrical efficiency in a waste combustion plant were performed. Furthermore, one objective of the study was to investigate the possibilities of improving waste bottom ash leaching properties by use of a rotary kiln treatment. The project work included construction of a bench-scale rotary kiln, performing ash rotary kiln treatment experiments, conducting gas suction probe measurements on a waste incineration plant and making some concept evaluations. The influence of the rotary kiln thermal treatment on the leaching of Ca, Al, Si, Mg, Ba, Sr, Cl, Cu, Pb, Zn, Cr, Mo, sulfate, DOC and carbonate was determined. As a result of these tests, the rotary kiln thermal treatment of bottom ashes can be recommended for reducing the leaching of Cu, Pb, Cl, Zn and DOC; however, an increased leaching of Cr and Mo should be expected. The combustion conditions above the grate of a waste incineration plant were investigated and the release and concentration of volatile ash species in the flue gas such as Cl, Na, K, Ca, Pb, Zn and S were measured. The conducted measurements show that flue gas from grate sections 3 and 4 can produce a sufficiently hot flue gas that contains only low concentrations of corrosive species, and therefore can be used to increase superheater temperatures. Implementation of the so-called flue gas split concept together with other steam circle modifications on a waste combustion plant, and using a reasonable increase in final steam temperature from 400 to 500 deg. C, have the potential to increase electrical efficiency from 24 to 30% (with respect to lower fuel heating value) in a waste combustion plant. (Author)

Tomatoes in oil recovery. [Plant waste additives improve yield

Energy Technology Data Exchange (ETDEWEB)

1981-01-01

The waste from processing tomato, squash and pepper stalks found unexpected use in recovery of oil. Even a negligible amount thereof in an aqueous solution pumped into an oil-bearing formation turned out to be sufficient to increase the yield. Substances of plant origin, which improve dramatically the oil-flushing properties of water, not only increase the recovery of oil, but reduce the volume of fluid to be pumped into the stratum. The staff of the Institute of Deep Oil and Gas Deposits of the Azerbaijan Academy of Sciences, who proved the technological and economical advantages of using the waste from plant processing, transmitted their findings to the oil workers of Baku. The scientists have concluded that there is a good raw material base in this republic for utilizing this method on oil-bearing formations.

Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

Energy Technology Data Exchange (ETDEWEB)

Larsson, Arne; Lidar, Per [Studsvik Nuclear AB, SE-611 82 Nykoeping (Sweden); Bergh, Niklas; Hedin, Gunnar [Westinghouse Electric Sweden AB, Fredholmsgatan 2, SE-721 63, Vaesteraas (Sweden)

2013-07-01

Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid

Waste Management Strategy for Dismantling Waste to Reduce Costs for Power Plant Decommissioning - 13543

International Nuclear Information System (INIS)

Larsson, Arne; Lidar, Per; Bergh, Niklas; Hedin, Gunnar

2013-01-01

Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named 'ndcon' to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

IAEA provisional code of practice on management of radioactive waste from nuclear power plants

International Nuclear Information System (INIS)

1982-10-01

This Code of Practice defines the minimum requirements for operations and design of structures, systems and components important for management of wastes from thermal nuclear power plants. It emphasizes what safety requirements shall be met rather than specifies how these requirements can be met; the latter aspect is covered in Safety Guides. The Code defines the need for a Government to assume responsibility for regulating waste management practices in conjunction with the regulation of a nuclear power plant. The Code does not prejudge the organization of the regulatory authority, which may differ from one Member State to another, and may involve more than one body. Similarly, the Code does not deal specifically with the functions of a regulatory authority responsible for such matters, although it may be of value to Member States in providing a basis for consideration of such functions. The Code deals with the entire management system for all wastes from nuclear power plants embodying thermal reactors including PWR, BWR, HWR and HTGR technologies. Topics included are: design, normal and abnormal operation, and regulation of management systems for gaseous, liquid and solid wastes, including decommissioning wastes. The Code includes measures to be taken with regard to the wastes arising from spent fuel management at nuclear power plants. However, the options for further management of spent fuel are only outlined since it is the subject of decisions by individual Member States. The Code does not require that an option(s) be decided upon prior to construction or operation of a nuclear power plant

Some contributions to the examination of composites from power plant wastes

Directory of Open Access Journals (Sweden)

Trifunović Prvoslav

2015-01-01

Full Text Available This paper describes an investigation into the possibilities of the use of all three types of solid power plant wastes: fly ash (FA, flue gas desulphurization gypsum (FGD gypsum and bottom ash (BA as components of composites for road construction. Two mixtures were made: 1. power plant wastes - Portland cement (PC and 2. power plant wastes - sand (S - Portland cement (PC. The mass ratio of components in these mixtures was: 1. FA - FGD gypsum - BA - PC = 2 : 1.5 : 5 : 1.5 and 2. FA- FGD gypsum-BA - S - PC= 2 : 1.5 : 4 : 1 : 1.5. For both mixtures, the compressive strength, the mineralogical composition, the water absorption and the resistance to freeze-thaw treatment were determined 7 and 28 days after preparation of samples (mixing with water. The obtained results showed that both mixtures could have potential to be used for sub-base layers in road construction and the second mixture (with natural aggregate-sand has advantage over the first mixture in terms of compressive strength, mineralogical composition, and resistance to freeze-thaw treatment.

Solid Waste from Four-stroke Medium Speed Engine Power Plant Operation

OpenAIRE

Smart, Heidi

2016-01-01

This thesis is a study of the solid-state waste generated in power plants based on internal combustion engine (ICE) technology, supplied by the Wärtsilä Energy Solutions division. This thesis, which characterizes and quantifies the waste, was done to enhance the ability of supporting customers in issues related to social and environmental impact assessment, environmental permits, waste management planning, etc. The Performance Standards on Environmental and Social Sustainability and the E...

Utilization of waste heat from nuclear power plants in agriculture

International Nuclear Information System (INIS)

Horacek, P.

1981-01-01

The development of nuclear power will result in the relative and absolute increase in the amount of waste heat which can be used in agriculture for heating greenhouses, open spaces, for fish breeding in heated water, for growing edible mushrooms, growing algae, for frost protection of orchards, air conditioning of buildings for breeding livestock and poultry, and for other purposes. In addition of the positive effect of waste heat, the danger increases of disease, weeds and pests. Pilot plant installations should be build in Czechoslovakia for testing the development of waste heat utilization. (Ha)

Effect of Different Organic Wastes on Soil Propertie s and Plant Growth and Yield: a Review

Directory of Open Access Journals (Sweden)

Hossain M. Z.

2017-12-01

Full Text Available The use of organic wastes in agriculture plays a great role in recycling essential plant nutrients, sustaining soil security as well as protecting the environment from unwanted hazards. This review article deals with the effect of different kinds of organic wastes on soil properties and plant growth and yield. Municipal solid waste is mainly used as a source of nitrogen and organic matter, improving soil properties and microbial activity that are closely related to soil fertility. Biowaste and food waste increase pH, nitrogen content, cation exchange capacity, water holding capacity, and microbial biomass in soil. Sewage sludge contains various amounts of organic matter and huge amounts of plant nutrients. Manure is a common waste which improves soil properties by adding nutrients and increases microbial and enzyme activity in soil. It also reduces toxicity of some heavy metals. These organic wastes have a great positive impact on soil physical, chemical, and biological properties as well as stimulate plant growth and thus increase the yield of crops.

Comparison of environmental impact of waste disposal from fusion, fission and coal-fired power plants

Energy Technology Data Exchange (ETDEWEB)

Frey, Bruno [Fichtner GmbH und Co. KG, Stuttgart (Germany)

2011-08-15

The radiotoxic hazard of waste from fusion power plants has been compared with that of fission power and radioactive trace elements in coal ash within some research programs such as SEAFP and SEIF. Within another program, in 2005 a Power Plant Conceptual Study (PPCS) has been finalized investigating 4 fusion power plant models A to D. In this paper, the radiotoxicity of model B is compared with a fission power plant, concentrating on the production of wastes. The hazard of the respective masses of enriched uranium before use in a fission power plant and coal ash of a power plant generating the same amount of electricity are used as benchmarks. It is evident that the development of ingestion and inhalation hazard of the PPCS model B is different from the results of earlier studies because of different assumptions on material impurities and other constraints. An important aspect is the presence of actinides in fusion power plant waste. (orig.)

Pilot plant study for treating sewage in the waste water treatment plant at Crevillente-Derramador, Alicante, Spain; Estudio con plant piloto para el tratamiento de aguas residuales en la EDAR de Crevillente-Derramador (Alicante)

Energy Technology Data Exchange (ETDEWEB)

Morenilla Martinez, J. J.; Bernacer Bonora, I.; Santos Asensi, J. M.; Martinez Muro, M. A.; Sanchez Ventral, A.; Martinez Cosin, J. M.

2002-07-01

It is much easier to carry out preliminary studies before a waste water treatment plant is built or enlarged or to identify existing problems and their possible solutions by using a portable pilot plant that is capable of operating under real conditions using the actual waste water that is causing the problem. A pilot plant was used to conduct treatability studies on the ground in the waste water treatment plant at Crevillente-Derramador, Alicante, Spain. The project was set up and directed by the Public Waste Water Treatment Agency of the Autonomous Community of Valencia. The work was aimed at finding a solution to existing problems in the plant and in pre dimensioning its future facilities. (Author) 8 refs.

Utilization of waste coconut coir dust as a source of fuel

Energy Technology Data Exchange (ETDEWEB)

Festin, T.F.; Jose, W.I.

1979-01-01

A review on the production of a gaseous fuel by the pyrolysis of waste coir dust, which is a by-product in the manufacturing of coir fibers from coconut husks. Experimental and pilot-plant studies on the pyrolysis of coir dust are discussed and the properties of the dust and the fuel gas produced are given. (Refs. 13).

Solidification of Savannah River Plant high level waste

International Nuclear Information System (INIS)

Maher, R.; Shafranek, L.F.; Kelley, J.A.; Zeyfang, R.W.

1981-11-01

Authorization for construction of the Defense Waste Processing Facility (DWPF) is expected in FY 83. The optimum time for stage 2 authorization is about three years later. Detailed design and construction will require approximately five years for stage 1, with stage 2 construction completed about two to three years later. Production of canisters of waste glass would begin in 1988, and the existing backlog of high level waste sludge stored at SRP would be worked off by about the year 2000. Stage 2 operation could begin in 1990. The technology and engineering are ready for construction and eventual operation of the DWPF for immobilizing high level radioactive waste at Savannah River Plant (SRP). Proceeding with this project will provide the public, and the leadership of this country, with a crucial demonstration that a major quantity of existing high level nuclear wastes can be safely and permanently immobilized. Early demonstration will both expedite and facilitate rational decision making on this aspect of the nuclear program. Delay in providing these facilities will result in significant DOE expenditures at SRP for new tanks just for continued temporary storage of wastes, and would probably result in dissipation of the intellectual and planning momentum that has built up in developing the project

Scientific, institutional, regulatory, political, and public acceptance of the waste isolation pilot plant transuranic waste repository

International Nuclear Information System (INIS)

Eriksson, L.G.

2000-01-01

The recent successful certification and opening of a first-of-a-kind, deep geological repository for safe disposal of long-lived, transuranic radioactive waste (TRUW) at the Waste Isolation Pilot Plant (WIPP) site, New Mexico, United States of America (USA), embody both long-standing local and wide-spread, gradually achieved, scientific, institutional, regulatory, political, and public acceptance. The related historical background and development are outlined and the main contributors to the successful siting, certification, and acceptance of the WIPP TRUW repository, which may also serve as a model to success for other radioactive waste disposal programs, are described. (author)

Investigation of the management of the wastes from plant accident

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-08-15

The accident in Fukushima Daiichi Nuclear Power Plant discharged large amount of radio-nuclides and contaminated wide areas in and out of the site. The decontamination, storage, treatment and disposal of generated wastes are now under planning. Though regulations for the radioactive wastes arisen from normal operation and decommissioning of nuclear facilities have been prepared, it is necessary to make amendment of those regulations to deal with wastes from the severe accident which may have much different features on nuclides contents, or possible accompanying hazardous chemical materials. Characteristics of wastes from accidents in foreign nuclear installations, and the treatment and the disposal of those wastes were surveyed by literature and radionuclide migration from the assumed temporally storage yards of the disaster debris was analyzed for consideration of future regulation. (author)

The waste isolation pilot plant regulatory compliance program

International Nuclear Information System (INIS)

Mewhinney, J.A.; Kehrman, R.F.

1996-01-01

The passage of the WIPP Land Withdrawal Act of 1992 (LWA) marked a turning point for the Waste Isolation Pilot Plant (WIPP) program. It established a Congressional mandate to open the WIPP in as short a time as possible, thereby initiating the process of addressing this nation's transuranic (TRU) waste problem. The DOE responded to the LWA by shifting the priority at the WIPP from scientific investigations to regulatory compliance and the completion of prerequisites for the initiation of operations. Regulatory compliance activities have taken four main focuses: (1) preparing regulatory submittals; (2) aggressive schedules; (3) regulator interface; and (4) public interactions

Liquid radioactive waste processing system for pressurized water reactor plants

International Nuclear Information System (INIS)

Anon.

1976-01-01

This Standard sets forth design, construction, and performance requirements, with due consideration for operation, of the Liquid Radioactive Waste Processing System for pressurized water reactor plants for design basis inputs. For the purpose of this Standard, the Liquid Radioactive Waste Processing System begins at the interfaces with the reactor coolant pressure boundary and the interface valve(s) in lines from other systems, or at those sumps and floor drains provided for liquid waste with the potential of containing radioactive material; and it terminates at the point of controlled discharge to the environment, at the point of interface with the waste solidification system, and at the point of recycle back to storage for reuse

Two Legionnaires' disease cases associated with industrial waste water treatment plants: a case report

Directory of Open Access Journals (Sweden)

Putus Tuula

2010-12-01

Full Text Available Abstract Background Finnish and Swedish waste water systems used by the forest industry were found to be exceptionally heavily contaminated with legionellae in 2005. Case presentation We report two cases of severe pneumonia in employees working at two separate mills in Finland in 2006. Legionella serological and urinary antigen tests were used to diagnose Legionnaires' disease in the symptomatic employees, who had worked at, or close to, waste water treatment plants. Since the findings indicated a Legionella infection, the waste water and home water systems were studied in more detail. The antibody response and Legionella urinary antigen finding of Case A indicated that the infection had been caused by Legionella pneumophila serogroup 1. Case A had been exposed to legionellae while installing a pump into a post-clarification basin at the waste water treatment plant of mill A. Both the water and sludge in the basin contained high concentrations of Legionella pneumophila serogroup 1, in addition to serogroups 3 and 13. Case B was working 200 meters downwind from a waste water treatment plant, which had an active sludge basin and cooling towers. The antibody response indicated that his disease was due to Legionella pneumophila serogroup 2. The cooling tower was the only site at the waste water treatment plant yielding that serogroup, though water in the active sludge basin yielded abundant growth of Legionella pneumophila serogroup 5 and Legionella rubrilucens. Both workers recovered from the disease. Conclusion These are the first reported cases of Legionnaires' disease in Finland associated with industrial waste water systems.

Impact of imidacloprid residues on the development of Eisenia fetida during vermicomposting of greenhouse plant waste.

Science.gov (United States)

Fernández-Gómez, Manuel J; Romero, Esperanza; Nogales, Rogelio

2011-09-15

Pesticide application in agriculture causes residues in post-harvest plant waste at different concentrations. Knowledge concerning how pesticide concentrations in such waste affect earthworms is essential for recycling greenhouse plant debris through vermicomposting. Here, we have evaluated the effects of imidacloprid (IMD) residues on earthworms (Eisenia fetida) during the vermicomposting of plant waste from greenhouse crops in Spain. Before, the effect of different IMD concentrations on earthworms was tested using cattle manure as an optimum waste for worm development. The results after using cattle manure indicate that IMD dose ≥ 5 mg kg(-1) hinders worm growth and even causes death, whereas IMD dose ≤ 2 mg IMD kg(-1) allows worm growth similar to control but impedes reproduction. The results from the vermicomposting of plant waste reveal that IMD inhibits adequate worm growth and increases mortality. Although 89% worms became sexually mature in substrate containing 2 mg IMD kg(-1), they did not produce cocoons. IMD also affected microorganisms harboured in the substrates for vermicomposting, as indicated by the reduction in their dehydrogenase activity. This enzyme activity was restored after vermicomposting. This study provides a sound basis for the vermicomposting of pesticide-contaminated plant waste. Copyright © 2011 Elsevier B.V. All rights reserved.

Co-combustor: the solid waste thermal treatment plant in MINT

International Nuclear Information System (INIS)

Norasalwa Zakaria; Mohd Azman Che Mat Isa; Sivapalan Kathiravale; Mohd Fairus Abdul Farid; Mohamad Puad Hj Abu; Rosli Darmawan; Muhd Noor Muhd Yunus

2005-01-01

MINT has geared up into the field of solid waste thermal treatment processing back in 1999 when a new unit known as MIREC was established. Since then, a fast progress has taken place including the design and construction of a pilot scale incinerator, named as the Co-Combustor. The Co-combustor was designed and developed based on the gasification principles, which employs combustion in starved air condition. In year 2001, this plant was commissioned. To date, it has been running quite well according to its design values. Several test runs were also performed in order to collect and gather data, which serve as a background or backtrack record for upgrading purposes and optimizing its performance in future. On going research is also conducted on this plant especially on the study of the waste's behaviors under combustion. Besides the typical RND activities, the Co-combustor is also currently being used to burn waste paper especially to dispose restricted and confidential documents. This paper will highlight on the design, performance, application and usage of the co-combustor. The direction for research and development activities for this plant is also discussed in this paper so as to strengthen the knowledge and build up expertise in the field of incineration

Plant oils thymol and eugenol affect cattle and swine waste emissions differently.

Science.gov (United States)

Varel, V H; Miller, D N; Lindsay, A D

2004-01-01

Wastes generated from the production of cattle and swine in confined facilities create the potential for surface and groundwater pollution, emission of greenhouse gases, transmission of pathogens to food and water sources, and odor. It is our hypothesis that something which inhibits microbial fermentation in livestock wastes will be beneficial to solving some of the environmental problems. Our work has concentrated on the use of antimicrobial plant oils, thymol, thyme oil, carvacrol, eugenol and clove oil. Anaerobic one-litre flasks with a working volume of 0.5 L cattle or swine manure were used to evaluate the effect of thymol and eugenol on production of fermentation gas, short-chain volatile fatty acids, lactate, and bacterial populations. Either oil at 0.2% in both wastes essentially stopped all production of gas and volatile fatty acids, and eliminated all fecal coliform bacteria. In cattle but not swine waste, thymol prevented the accumulation of lactate. However, eugenol stimulated lactate formation in cattle and swine wastes. Thus, eugenol may offer a distinct advantage over thymol, because lactate accumulation in the wastes causes the pH to drop more rapidly, further inhibiting microbial activity and nutrient emissions. We conclude that plant oils may offer solutions to controlling various environmental problems associated with livestock wastes, assuming that they are cost-effective.

Radioactive waste disposal: Waste Isolation Pilot Plants (WIPP). March 1978-November 1989 (Citations from the NTIS data base). Report for Mar 78-Nov 89

International Nuclear Information System (INIS)

1990-01-01

This bibliography contains citations concerning the Waste Isolation Pilot Plant (WIPP), a geologic repository located in New Mexico for transuranic wastes generated by the U.S. Government. Articles follow the development of the program from initial site selection and characterization through construction and testing, along with research programs on environmental impacts, structural design, and radionuclide landfill gases. Existing plants and facilities, pilot plants, migration, rock mechanics, economics, regulations, and transport of wastes to the site are also included. The Salt Repository Project and the Crystalline Repository Project are referenced in related published bibliographies. (Contains 184 citations fully indexed and including a title list.)

Advanced techniques for analytic liquid wastes management in the Rokkasho reprocessing plant

International Nuclear Information System (INIS)

Madic, C.; Moulin, J.P.; Runge, S.; Schott, R.; Kashiwai, T.; Hayashi, M.

1991-01-01

The JNFS Rokkasho reprocessing plant is a large scale commercial reprocessing plant. Liquid waste treatment relies on concentration by evaporation. The management of liquid wastes is rather sophisticated and implies, beside the organic wastes, sorting out between process and non-process, acidic and salt-bearing, tritiated and low tritiated streams and also according to their level of activity. A particular attention had to be paid to the analytical wastes, as their particularity is to contain not only a significant amount of radioactivity but also some fissile material and exotic chemicals which are useful for analytical purpose but unwanted in the main process mainly because of their corrosive and chelating properties. The analytical wastes are sorted out according to their activity level and fissile material content. On the one hand, a specific process has been developed to recover the bulk of plutonium from the analytical wastes. On the other hand, the foreseeable amount of unwanted chemicals (such as chloride ions) has been drastically reduced by carefully selecting all the analytical methods either by modification of already known methods or in some cases by working out new methods

Development of recycling techniques for nuclear power plant decommissioning waste

International Nuclear Information System (INIS)

Ishikura, Takeshi; Oguri, Daiichiro; Abe, Seiji; Ohnishi, Kazuhiko

2003-01-01

Recycling of concrete and metal waste will provide solution to reduce waste volume, contributing to save the natural resources and to protect the environment. Nuclear Power Engineering Corporation has developed techniques of concrete and metal recycling for decommissioning waste of commercial nuclear power plants. A process of radioactive concrete usage for mortar solidification was seen to reduce concrete waste volume by 2/3. A concrete reclamation process for high quality aggregate was confirmed that the reclaimed aggregate concrete is equivalent to ordinary concrete. Its byproduct powder was seen to be utilized various usage. A process of waste metal casting to use radioactive metal as filler could substantially decrease the waste metal volume when thinner containers are applied. A pyro-metallurgical separation process was seen to decrease cobalt concentration by 1/100. Some of these techniques are finished of demonstration tests for future decommissioning activity. (author)

Preoperational checkout of the remote-handled transuranic waste handling at the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1987-09-01

This plan describes the preoperational checkout for handling Remote-Handled Transuranic (RH-TRU) Wastes from their receipt at the Waste Isolation Pilot Plant (WIPP) to their emplacement underground. This plan identifies the handling operations to be performed, personnel groups responsible for executing these operations, and required equipment items. In addition, this plan describes the quality assurance that will be exercised throughout the checkout, and finally, it establishes criteria by which to measure the success of the checkout. 7 refs., 5 figs

Waste Isolation Pilot Plant CY 2000 Site Environmental Report

International Nuclear Information System (INIS)

Westinghouse TRU Solutions, LLC; Environmental Science and Research Foundation, Inc.

2001-01-01

The U.S. Department of Energy's (DOE) Carlsbad Field Office and Westinghouse TRU Solutions, LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2000 Site Environmental Report summarizes environmental data from calendar year (CY) 2000 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T), and the Waste Isolation Pilot Plant Environmental Protect ion Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2000. The format of this report follows guidance offered in a June 1, 2001 memo from DOE's Office of Policy and Guidance with the subject ''Guidance for the preparation of Department of Energy (DOE) Annual Site Environmental Reports (ASERs) for Calendar Year 2000.'' WIPP received its first shipment of waste on March 26, 1999. In 2000, no evidence was found of any adverse

Waste Isolation Pilot Plant CY 2000 Site Environmental Report

Energy Technology Data Exchange (ETDEWEB)

Westinghouse TRU Solutions, LLC; Environmental Science and Research Foundation, Inc.

2001-12-31

The U.S. Department of Energy's (DOE) Carlsbad Field Office and Westinghouse TRU Solutions, LLC (WTS) are dedicated to maintaining high quality management of Waste Isolation Pilot Plant (WIPP) environmental resources. DOE Order 5400.1, General Environmental Protection Program, and DOE Order 231.1, Environmental, Safety, and Health Reporting, require that the environment at and near DOE facilities be monitored to ensure the safety and health of the public and the environment. This Waste Isolation Pilot Plant 2000 Site Environmental Report summarizes environmental data from calendar year (CY) 2000 that characterize environmental management performance and demonstrate compliance with federal and state regulations. This report was prepared in accordance with DOE Order 5400.1, DOE Order 231.1, the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T), and the Waste Isolation Pilot Plant Environmental Protect ion Implementation Plan (DOE/WIPP 96-2199). The above orders and guidance documents require that DOE facilities submit an Annual Site Environmental Report to DOE Headquarters, Office of the Assistant Secretary for Environment, Safety, and Health. The purpose of this report is to provide a comprehensive description of operational environmental monitoring activities, to provide an abstract of environmental activities conducted to characterize site environmental management performance to confirm compliance with environmental standards and requirements, and to highlight significant programs and efforts of environmental merit at WIPP during CY 2000. The format of this report follows guidance offered in a June 1, 2001 memo from DOE's Office of Policy and Guidance with the subject ''Guidance for the preparation of Department of Energy (DOE) Annual Site Environmental Reports (ASERs) for Calendar Year 2000.'' WIPP received its first shipment of waste on March 26, 1999. In 2000, no

Supply, operation and radioactive waste disposal of nuclear power plants

International Nuclear Information System (INIS)

Mohrhauer, H.; Krey, M.; Haag, G.; Wolters, J.; Merz, E.; Sauermann, P.F.

1981-07-01

The subject of 'Nuclear Fuel Cycle' is treated in 5 reports: 1. Uranium supply; 2. Fabrication and characteristics of fuel elements; 3. Design, operation and safety of nuclear power plants after Harrisburg; 4. Radioactive waste disposal of nuclear power plants - changed political scenery after 1979; 5. Shutdown and dismantling of LWR-KKW - state of knowledge and feasibility. (HP) [de

Leachability of radionuclides from cement solidified waste forms produced at operating nuclear power plants

International Nuclear Information System (INIS)

Croney, S.T.

1985-03-01

This study determined the leachability indexes of radionuclides contained in solidified liquid wastes from operating nuclear power plants. Different sizes of samples of cement-solidified liquid wastes were collected from two nuclear power plants - a pressurized water reactor and a boiling water reactor - to correlate radionuclide leaching from small- and full-sized (55-gallon) waste forms. Diffusion-based model analysis (ANS 16.1) of measured radionuclide leach data from both small- and full-sized samples was performed and indicate that leach data from small samples can be used to determine leachability indexes for full-sizes waste forms. The leachability indexes for cesium, strontium, and cobalt isotopes were determined for waste samples from both plants according to the models used for ANS 16.1. The leachability indexes for the pressurized water reactor samples were 6.4 for cesium, 7.1 for strontium, and 10.4 for cobalt. Leachability indexes for the boiling water reactor samples were 6.5 for cesium, 8.6 for strontium, and 11.1 for cobalt

French industrial plant AVM for continuous vitrification of high level radioactive wastes

International Nuclear Information System (INIS)

Bonniaud, Roger; Sombret, Claude; Barbe, Alain

1975-01-01

The A.V.M. plant is a continuous process plant now under construction at Marcoule and intended for vitrifying the whole of fission product solutions from the C.E.A. (Commissariat a l'Energie Atomique) - Marcoule reprocessing plant. The outset of the construction took place in the second 1974 half year; the first radioactive run is scheduled in July 1977. The two steps of the process are shown: first a continuous calcination then a continuous glass making from the calcined product and suitable additives. The plant consists in two parts: vitrification and storage facilities. Some wastes will be continuously produced day after day due to gas clean up and worn out materials. Characteristics of the solutions processed, calcined products, glass composition, and expected liquid wastes are given in tables [fr

Preparation and characterization of corn reinforced polymer sheet of fibers; Obtencao e caracterizacao de polimero reforcado com fibras da folha de milho

Energy Technology Data Exchange (ETDEWEB)

Moreira, Tatiana Martinez; Seo, Emilia Satoshi Miyamaru, E-mail: tatianaltda@hotmail.com, E-mail: esmiyseo@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2016-10-15

There is a global trend in seeking plant fibers to replace the synthetic fibers to obtain reinforced composites aimed at the use of renewable resources. In this context, this paper aims to develop the process of preparing maize leaf fibers, characterizing them and adapting them for applications in the construction industry and develop a reinforced polymer composite with these fibers. Corn leaves were dried in environmental temperature, treated by mercerizing, then neutralized with acid solution and washed in running water. The characterization of the corn leaf fibers was carried out by X-ray diffraction, X-ray fluorescence, scanning electron microscopy, specific surface area, thermogravimetry and specific mass. The mercerizing treatment was effective, because the maize fibers have characteristics similar to synthetic fibers, leading to a possibility of new technological uses. The polymeric composite material was developed by extrusion processes and injection and tested for tensile testing, differential scanning calorimetry and scanning electron microscopy, thus reused an organic waste that would be disposed of by inserting it in a technological process, contributing to the research and development of new polymeric materials as well as to reduce waste discarded as scrap. (author)

Waste Isolation Pilot Plant No-migration variance petition. Addendum: Volume 7, Revision 1

Energy Technology Data Exchange (ETDEWEB)

1990-03-01

This report describes various aspects of the Waste Isolation Pilot Plant (WIPP) including design data, waste characterization, dissolution features, ground water hydrology, natural resources, monitoring, general geology, and the gas generation/test program.

USE MANURE AND ORGANIC WASTE AS PLANTING MEDIA OF SEED POTATOES PRODUCTION

Directory of Open Access Journals (Sweden)