Nevada National Security Site Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

none,

2013-06-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: • DOE hazardous and non-hazardous non-radioactive classified waste • DOE low-level radioactive waste (LLW) • DOE mixed low-level waste (MLLW) • U.S. Department of Defense (DOD) classified waste The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2013-01-01

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: DOE hazardous and non-hazardous non-radioactive classified waste; DOE low-level radioactive waste (LLW); DOE mixed low-level waste (MLLW); and, U.S. Department of Defense (DOD) classified waste. The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

Hanford Immobilized Low-Activity Waste Product Acceptance Test Plan

International Nuclear Information System (INIS)

Peeler, D.

1999-01-01

'The Hanford Site has been used to produce nuclear materials for the U.S. Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during Pu production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The DOE is proceeding with an approach to privatize the treatment and immobilization of Handord''s LAW and HLW.'

Waste transmutation and public acceptance

International Nuclear Information System (INIS)

Pigford, T.H.

1991-01-01

The concept of transmuting radioactive wastes with reactors or accelerators is appealing. It has the potential of simplifying or eliminating problems of disposing of nuclear waste. The transmutation concept has been renewed vigorously at a time when national projects to dispose of high-level and transuranic waste are seriously delayed. In this period of tightening federal funds and program curtailments, skilled technical staffs are available at US Department of Energy (DOE) national laboratories and contractors to work on waste transmutation. If the claims of transmutation can be shown to be realistic, economically feasible, and capable of being implemented within the US institutional infrastructure, public acceptance of nuclear waste disposal may be enhanced. If the claims for transmutation are not substantiated, however, there will result a serious loss of credibility and an unjust exacerbation of public concerns about nuclear waste. The paper discusses the following topics: how public acceptance is achieved; the technical community and waste disposal; transmutation and technical communication; transmutation issues; technical fixes and public perception

Hanford Immobilized Low-Activity Waste Product Acceptance Test Plan

Energy Technology Data Exchange (ETDEWEB)

Peeler, D.

1999-06-22

'The Hanford Site has been used to produce nuclear materials for the U.S. Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during Pu production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The DOE is proceeding with an approach to privatize the treatment and immobilization of Handord''s LAW and HLW.'

Managing Hanford Site solid waste through strict acceptance criteria

International Nuclear Information System (INIS)

Jasen, W.G.; Pierce, R.D.; Willis, N.P.

1993-02-01

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA) and the Resource Conservation and Recovery Act of 1976 (RCRA) have led to the definition of a group of wastes called radioactive mixed wastes (RMW). As a result of the radioactive and hazardous properties of these wastes, strict management programs have been implemented for the management of these wastes. Solid waste management is accomplished through a systems performance approach to waste management that used best-demonstrated available technology (BDAT) and best management practices. The solid waste program at the Hanford Site strives to integrate all aspects of management relative to the treatment, storage and disposal (TSD) of solid waste. Often there are many competing and important needs. It is a difficult task to balance these needs in a manner that is both equitable and productive. Management science is used to help the process of making decisions. Tools used to support the decision making process include five-year planning, cost estimating, resource allocation, performance assessment, waste volume forecasts, input/output models, and waste acceptance criteria. The purpose of this document is to describe how one of these tools, waste acceptance criteria, has helped the Hanford Site manage solid wastes

Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

W. Mahlon Heileson

2006-10-01

The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

Waste-acceptance criteria for greater confinement disposal

International Nuclear Information System (INIS)

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

1987-01-01

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

Waste-acceptance criteria for greater-confinement disposal

International Nuclear Information System (INIS)

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

1986-01-01

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

Waste acceptance and impact ON D and D in Switzerland

International Nuclear Information System (INIS)

Maxeiner, Harald

2002-01-01

Harald Maxeiner described clearance and waste conditioning requirements in Switzerland, and their impacts on decommissioning: Although decommissioning of the first (oldest) reactor will not take place until 2009 at the earliest (hypothetical operating lifetime of 40 years), detailed decommissioning studies have to be carried out today, in order to demonstrate the feasibility of the technologies to be used and to determine anticipated costs (for the purpose of calculating financial contributions to a decommissioning fund). The studies are based on waste acceptance criteria and guidelines that apply to waste already in existence. The focus is on preparing inventories of activated and contaminated components and conditioning of these components. The basis for present and future conditioning of radioactive wastes, as well as for their interim storage and final disposal, is provided by the official guideline HSK R-14. According to this guideline, raw waste requires to be solidified (inter alia with cement) and the resulting waste product must: remain intact until final disposal, not be readily dispersible, be resistant to aqueous media, not be readily combustible, not contain any unnecessary voids, contain as little organic material as possible. The waste package containing the waste product must: constitute a further barrier to dispersion, outlast (at least) interim storage, be documented with details of manufacturing, composition, properties, be designed to resist corrosion using suitable materials, be characterised by a quality assurance program for raw waste, waste product and waste package. The only possible reasons for interim storage of waste without solidification are: decay storage followed by conventional waste management, if waste packages fulfil acceptance criteria for the final repository without further treatment, if, in the foreseeable future, an alternative conditioning method can be expected. The guidelines and acceptance criteria mentioned set strict

Waste-acceptance criteria and risk-based thinking for radioactive-waste classification

International Nuclear Information System (INIS)

Lowenthal, M.D.

1998-01-01

The US system of radioactive-waste classification and its development provide a reference point for the discussion of risk-based thinking in waste classification. The official US system is described and waste-acceptance criteria for disposal sites are introduced because they constitute a form of de facto waste classification. Risk-based classification is explored and it is found that a truly risk-based system is context-dependent: risk depends not only on the waste-management activity but, for some activities such as disposal, it depends on the specific physical context. Some of the elements of the official US system incorporate risk-based thinking, but like many proposed alternative schemes, the physical context of disposal is ignored. The waste-acceptance criteria for disposal sites do account for this context dependence and could be used as a risk-based classification scheme for disposal. While different classes would be necessary for different management activities, the waste-acceptance criteria would obviate the need for the current system and could better match wastes to disposal environments saving money or improving safety or both

Radwaste characteristics and Disposal Facility Waste Acceptance Criteria

International Nuclear Information System (INIS)

Sung, Suk Hyun; Jeong, Yi Yeong; Kim, Ki Hong

2008-01-01

The purpose of Radioactive Waste Acceptance Criteria (WAC) is to verify a radioactive waste compliance with radioactive disposal facility requirements in order to maintain a disposal facility's performance objectives and to ensure its safety. To develop WAC which is conformable with domestic disposal site conditions, we furthermore analysed the WAC of foreign disposal sites similar to the Kyung-Ju disposal site and the characteristics of various wastes which are being generated from Korea nuclear facilities. Radioactive WAC was developed in the technical cooperation with the Korea Atomic Energy Research Institute in consideration of characteristics of the wastes which are being generated from various facilities, waste generators' opinions and other conditions. The established criteria was also discussed and verified at an advisory committee which was comprised of some experts from universities, institutes and the industry. So radioactive WAC was developed to accept all wastes which are being generated from various nuclear facilities as much as possible, ensuring the safety of a disposal facility. But this developed waste acceptance criteria is not a criteria to accept all the present wastes generated from various nuclear facilities, so waste generators must seek an alternative treatment method for wastes which were not worth disposing of, and then they must treat the wastes more to be acceptable at a disposal site. The radioactive disposal facility WAC will continuously complement certain criteria related to a disposal concentration limit for individual radionuclide in order to ensure a long-term safety.

Hanford Site solid waste acceptance criteria

International Nuclear Information System (INIS)

Willis, N.P.; Triner, G.C.

1991-09-01

Westinghouse Hanford Company manages the Hanford Site solid waste treatment, storage, and disposal facilities for the US Department of Energy Field Office, Richland under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites, radioactive solid waste storage areas and hazardous waste treatment, storage, and/or disposal facilities. This manual defines the criteria that must be met by waste generators for solid waste to be accepted by Westinghouse Hanford Company for treatment, storage and/or disposal facilities. It is to be used by all waste generators preparing radioactive solid waste for storage or disposal at the Hanford Site facilities and for all Hanford Site generators of hazardous waste. This manual is also intended for use by Westinghouse Hanford Company solid waste technical staff involved with approval and acceptance of solid waste. The criteria in this manual represent a compilation of state and federal regulations; US Department of Energy orders; Hanford Site requirements; and other rules, regulations, guidelines, and standards as they apply to management of solid waste. Where appropriate, these requirements are included in the manual by reference. It is the intent of this manual to provide guidance to the waste generator in meeting the applicable requirements

Classification of radioactive waste and determination of waste specifications as well as conditions of acceptance for ultimate storage

International Nuclear Information System (INIS)

Merz, E.

1983-04-01

The determination of waste specification and conditions of acceptance must follow a certain scheme, the basics of which will be presented. First the types of waste and the ultimate storage facilities will be characterized. The various categories of waste will be listed in a universally valid system, and the preliminary conditioning options will be determined. Based on the results of safety analysis taking into account the whole system - geological circumstances, ultimate store mines, types and forms of waste - specifications for the various ultimate store products are to be derived following iterative methods. Suggestions though not of a binding nature and probably subject to eventual revisions in part will be presented. To ensure the safety goals, i.e. the exclusion of radioactivity from the human biosphere, appropriate quality control is required concerning the production and the acceptance at the ultimate store. The guiding principles to be heeded will be discussed in brief. (orig./HP) [de

Preliminary waste acceptance requirements - Konrad repository project

International Nuclear Information System (INIS)

Brennecke, P.W.; Warnecke, E.H.

1991-01-01

In Germany, the planned Konrad repository is proposed for the disposal of all types of radioactive wastes whose thermal influence upon the host rock is negligible. The Bundesamt fuer Strahlenschutz has established Preliminary Waste Acceptance Requirements (as of April 1990) for this facility. The respective requirements were developed on the basis of the results of site-specific safety assessments. They include general requirements on the waste packages to be disposed of as well as more specific requirements on the waste forms, the packaging and the radionuclide inventory per waste package. In addition, the delivery of waste packages was regulated. An outline of the structure and the elements of the Preliminary Waste Acceptance Requirements of April 1990 is given including comments on their legal status. (Author)

Nevada National Security Site Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2010-09-03

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2010-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

Nevada National Security Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

2011-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NNSSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NNSS Area 3 and Area 5 Radioactive Waste Management Complex for disposal. The NNSA/NSO and support contractors are available to assist you in understanding or interpreting this document. For assistance, please call the NNSA/NSO Waste Management Project at (702) 295-7063 or fax to (702) 295-1153.

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

Energy Technology Data Exchange (ETDEWEB)

NNSA/NSO Waste Management Project

2008-06-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

Nevada Test Site Waste Acceptance Criteria (NTSWAC)

International Nuclear Information System (INIS)

NNSA/NSO Waste Management Project

2008-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal

Nevada test site waste acceptance criteria

International Nuclear Information System (INIS)

1996-01-01

This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document

Nevada test site waste acceptance criteria

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

This document provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

Nevada Test Site Waste Acceptance Criteria

International Nuclear Information System (INIS)

U.S. Department of Energy, Nevada Operations Office, Waste Acceptance Criteria

1999-01-01

This document provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the Nevada Test Site

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.

US Department of Energy acceptance of commercial transuranic waste

International Nuclear Information System (INIS)

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

1980-02-01

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

Preliminary waste acceptance requirements for the planned Konrad repository

International Nuclear Information System (INIS)

Warnecke, E.; Brennecke, P.

1987-01-01

The Physikalisch-Technische Bundesanstalt (PTB) has established Preliminary Waste Acceptance Requirements for the planned Konrad repository. These requirements were developed, in accordance with the Safety Criteria of the Reactor Safety Commission, with the help of a site specific safety assessment; they are under the reservation of the plan approval procedure, which is still in progress. In developing waste acceptance requirements, the PTB fulfills one of its duties as the institute responsible for waste disposal and gives guidelines for waste conditioning to waste producers and conditioners. (orig.) [de

From waste packages acceptance criteria to waste packages acceptance process at the Centre de l'Aube disposal facility

International Nuclear Information System (INIS)

Dutzer, M.

2003-01-01

The Centre de l'Aube disposal facility has now been operated for 10 years. At the end of 2001, about 124,000 m3 of low and intermediate level short lived waste packages, representing 180,000 packages, have been disposed, for a total capacity of 1,000,000 m3. The flow of waste packages is now between 12 and 15,000 m3 per year, that is one third of the flow that was taken into account for the design of the repository. It confirms the efforts by waste generators to minimise waste production. This flow represents 25 to 30,000 packages, 50% are conditioned into the compaction facility of the repository, so that 17,000 packages are disposed per year. 54 disposal vaults have been closed. In 1996-1999, the safety assessment of the repository have been reviewed, taking into account the experience of operation. This assessment was investigated by the regulatory body and, subsequently, a so-called 'definitive license' to operate was granted to ANDRA on September 2, 1999 with updated licensing requirements. Another review will be performed in 2004. To ensure a better consistency with the safety assessment of the facility, Andra issued new technical requirements for waste packages at the end of 2000. Discussions with waste generators also showed that the waste package acceptance process should be improved to provide a more precise definition of operational criteria to comply with in waste conditioning facilities. Consequently, a new approach has been implemented since 2000. (orig.)

Radioactive waste disposal and public acceptance aspects

Energy Technology Data Exchange (ETDEWEB)

Ulhoa, Barbara M.A.; Aleixo, Bruna L.; Mourao, Rogerio P.; Ferreira, Vinicius V.M., E-mail: mouraor@cdtn.b, E-mail: vvmf@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2011-07-01

Part of the public opinion around the world considers the wastes generated due to nuclear applications as the biggest environmental problem of the present time. The development of a solution that satisfies everybody is a great challenge, in that obtaining public acceptance for nuclear enterprises is much more challenging than solving the technical issues involved. Considering that the offering of a final solution that closes the radioactive waste cycle has a potentially positive impact on public opinion, the objective of this work is to evaluate the amount of the radioactive waste volume disposed in a five-year period in several countries and gauge the public opinion regarding nuclear energy. The results show that the volume of disposed radioactive waste increased, a fact that stresses the importance of promoting discussions about repositories and public acceptance. (author)

Radioactive waste disposal and public acceptance aspects

International Nuclear Information System (INIS)

Ulhoa, Barbara M.A.; Aleixo, Bruna L.; Mourao, Rogerio P.; Ferreira, Vinicius V.M.

2011-01-01

Part of the public opinion around the world considers the wastes generated due to nuclear applications as the biggest environmental problem of the present time. The development of a solution that satisfies everybody is a great challenge, in that obtaining public acceptance for nuclear enterprises is much more challenging than solving the technical issues involved. Considering that the offering of a final solution that closes the radioactive waste cycle has a potentially positive impact on public opinion, the objective of this work is to evaluate the amount of the radioactive waste volume disposed in a five-year period in several countries and gauge the public opinion regarding nuclear energy. The results show that the volume of disposed radioactive waste increased, a fact that stresses the importance of promoting discussions about repositories and public acceptance. (author)

Quality assurance requirements and methods for high level waste package acceptability

International Nuclear Information System (INIS)

1992-12-01

This document should serve as guidance for assigning the necessary items to control the conditioning process in such a way that waste packages are produced in compliance with the waste acceptance requirements. It is also provided to promote the exchange of information on quality assurance requirements and on the application of quality assurance methods associated with the production of high level waste packages, to ensure that these waste packages comply with the requirements for transportation, interim storage and waste disposal in deep geological formations. The document is intended to assist both the operators of conditioning facilities and repositories as well as national authorities and regulatory bodies, involved in the licensing of the conditioning of high level radioactive wastes or in the development of deep underground disposal systems. The document recommends the quality assurance requirements and methods which are necessary to generate data for these parameters identified in IAEA-TECDOC-560 on qualitative acceptance criteria, and indicates where and when the control methods can be applied, e.g. in the operation or commissioning of a process or in the development of a waste package design. Emphasis is on the control of the process and little reliance is placed on non-destructive or destructive testing. Qualitative criteria, relevant to disposal of high level waste, are repository dependent and are not addressed here. 37 refs, 3 figs, 2 tabs

Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Management

2009-05-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

Nevada Test Site Waste Acceptance Criteria (NTSWAC), Rev. 7-01

International Nuclear Information System (INIS)

2009-01-01

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive waste and mixed low-level waste for disposal. The NTSWAC includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex for disposal.

Standardization of waste acceptance test methods by the Materials Characterization Center

International Nuclear Information System (INIS)

Slate, S.C.

1985-01-01

This paper describes the role of standardized test methods in demonstrating the acceptability of high-level waste (HLW) forms for disposal. Key waste acceptance tests are standardized by the Materials Characterization Center (MCC), which the US Department of Energy (DOE) has established as the central agency in the United States for the standardization of test methods for nuclear waste materials. This paper describes the basic three-step process that is used to show that waste is acceptable for disposal and discusses how standardized tests are used in this process. Several of the key test methods and their areas of application are described. Finally, future plans are discussed for using standardized tests to show waste acceptance. 9 refs., 1 tab

Nevada test site defense waste acceptance criteria, certification, and transfer requirements

International Nuclear Information System (INIS)

1988-10-01

The Nevada Test Site (NTS) Defense Waste Acceptance Criteria, Certification and Transfer Requirements establishes procedures and criteria for safe transfer, disposal, and storage of defense transuranic, low-level, and mixed waste at the NTS. Included are an overview of the NTS defense waste management program; the NTS waste acceptance criteria for transuranic, low-level, and mixed wastes; waste certification requirements and guidance; application to submit waste; and requirements for waste transfer and receipt. 5 figs., 16 tabs

Documentation of acceptable knowledge for LANL Plutonium Facility transuranic waste streams

International Nuclear Information System (INIS)

Montoya, A.J.; Gruetzmacher, K.; Foxx, C.; Rogers, P.S.Z.

1998-01-01

Characterization of transuranic waste from the LANL Plutonium Facility for certification and transportation to WIPP includes the use of acceptable knowledge as specified in the WIPP Quality Assurance Program Plan. In accordance with a site-specific procedure, documentation of acceptable knowledge for retrievably stored and currently generated transuranic waste streams is in progress at LANL. A summary overview of the transuranic waste inventory is complete and documented in the Sampling Plan. This document also includes projected waste generation, facility missions, waste generation processes, flow diagrams, times, and material inputs. The second part of acceptable knowledge documentation consists of assembling more detailed acceptable knowledge information into auditable records and is expected to require several years to complete. These records for each waste stream must support final assignment of waste matrix parameters, EPA hazardous waste numbers, and radionuclide characterization. They must also include a determination whether waste streams are defense waste streams for compliance with the WIPP Land Withdrawal Act. The LANL Plutonium Facility's mission is primarily plutonium processing in basic special nuclear material (SNM) research activities to support national defense and energy programs. It currently has about 100 processes ranging from SNM recovery from residues to development of plutonium 238 heat sources for space applications. Its challenge is to characterize and certify waste streams from such diverse and dynamic operations using acceptable knowledge. This paper reports the progress on the certification of the first of these waste streams to the WIPP WAC

Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

2005-01-01

The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source

Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant

Energy Technology Data Exchange (ETDEWEB)

Washington TRU Solutions LLC

2005-12-29

The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source

Multi-discipline Waste Acceptance Process at the Nevada National Security Site - 13573

Energy Technology Data Exchange (ETDEWEB)

Carilli, Jhon T. [US Department Of Energy, Nevada Site Office, P. O. Box 98518, Las Vegas, Nevada 89193-8518 (United States); Krenzien, Susan K. [Navarro-Intera, LLC, P. O. Box 98952, Las Vegas, Nevada 89193-8952 (United States)

2013-07-01

The Nevada National Security Site low-level radioactive waste disposal facility acceptance process requires multiple disciplines to ensure the protection of workers, the public, and the environment. These disciplines, which include waste acceptance, nuclear criticality, safety, permitting, operations, and performance assessment, combine into the overall waste acceptance process to assess low-level radioactive waste streams for disposal at the Area 5 Radioactive Waste Management Site. Four waste streams recently highlighted the integration of these disciplines: the Oak Ridge Radioisotope Thermoelectric Generators and Consolidated Edison Uranium Solidification Project material, West Valley Melter, and classified waste. (authors)

Identification of items and activities important to waste form acceptance by Westinghouse GoCo sites

International Nuclear Information System (INIS)

Plodinec, M.J.; Marra, S.L.; Dempster, J.; Randklev, E.H.

1993-01-01

The Department of Energy has established specifications (Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms, or WAPS) for canistered waste forms produced at Hanford, Savannah River, and West Valley. Compliance with these specifications requires that each waste form producer identify the items and activities which must be controlled to ensure compliance. As part of quality assurance oversight activities, reviewers have tried to compare the methodologies used by the waste form producers to identify items and activities important to waste form acceptance. Due to the lack of a documented comparison of the methods used by each producer, confusion has resulted over whether the methods being used are consistent. This confusion has been exacerbated by different systems of nomenclature used by each producer, and the different stages of development of each project. The waste form producers have met three times in the last two years, most recently on June 28, 1993, to exchange information on each producer's program. These meetings have been sponsored by the Westinghouse GoCo HLW Vitrification Committee. This document is the result of this most recent exchange. It fills the need for a documented comparison of the methodologies used to identify items and activities important to waste form acceptance. In this document, the methodology being used by each waste form producer is summarized, and the degree of consistency among the waste form producers is determined

Waste management facility acceptance - some findings

International Nuclear Information System (INIS)

Sigmon, B.

1987-01-01

Acceptance of waste management facilities remains a significant problem, despite years of efforts to reassure potential host communities. The tangible economic benefits from jobs, taxes, and expenditures are generally small, while the intangible risks of environmental or other impacts are difficult to evaluate and understand. No magic formula for winning local acceptance has yet been found. Limited case study and survey work does suggest some pitfalls to be avoided and some directions to be pursued. Among the most significant is the importance that communities place on controlling their own destiny. Finding a meaningful role for communities in the planning and operation of waste management facilities is a challenge that would-be developers should approach with the same creativity that characterizes their technical efforts

Attention: no radioactive waste accepted on 7 September

CERN Multimedia

2012-01-01

Anouncement by the RW section of the Radiation Protection Group: The Treatment Centre for Radioactive Waste will not be accepting waste on Friday, 7 September 2012. Thank you for adjusting your activities accordingly.

Nevada Test Site waste acceptance criteria [Revision 1

Energy Technology Data Exchange (ETDEWEB)

None

1997-08-01

Revision one updates the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document.

Nevada Test Site waste acceptance criteria [Revision 1

International Nuclear Information System (INIS)

None

1997-01-01

Revision one updates the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive and mixed waste for disposal; and transuranic and transuranic mixed waste for interim storage at the NTS. Review each section of this document. This document is not intended to include all of the requirements; rather, it is meant as a guide toward meeting the regulations. All references in this document should be observed to avoid omission of requirements on which acceptance or rejection of waste will be based. The Department of Energy/Nevada Operations Office (DOE/NV) and support contractors are available to assist you in understanding or interpreting this document

Anticipating Potential Waste Acceptance Criteria for Defense Spent Nuclear Fuel

International Nuclear Information System (INIS)

Rechard, R.P.; Lord, M.E.; Stockman, C.T.; McCurley, R.D.

1997-01-01

The Office of Environmental Management of the U.S. Department of Energy is responsible for the safe management and disposal of DOE owned defense spent nuclear fuel and high level waste (DSNF/DHLW). A desirable option, direct disposal of the waste in the potential repository at Yucca Mountain, depends on the final waste acceptance criteria, which will be set by DOE's Office of Civilian Radioactive Waste Management (OCRWM). However, evolving regulations make it difficult to determine what the final acceptance criteria will be. A method of anticipating waste acceptance criteria is to gain an understanding of the DOE owned waste types and their behavior in a disposal system through a performance assessment and contrast such behavior with characteristics of commercial spent fuel. Preliminary results from such an analysis indicate that releases of 99Tc and 237Np from commercial spent fuel exceed those of the DSNF/DHLW; thus, if commercial spent fuel can meet the waste acceptance criteria, then DSNF can also meet the criteria. In large part, these results are caused by the small percentage of total activity of the DSNF in the repository (1.5%) and regulatory mass (4%), and also because commercial fuel cladding was assumed to provide no protection

Acceptance issues for large items and difficult waste

International Nuclear Information System (INIS)

Palmer, J.; Lock, Peter

2002-01-01

Peter Lock described some particular cases which had given rise to difficult acceptance issues at NIREX, ranging from large size items to the impacts of chemicals used during decontamination on the mobility of radionuclides in a disposal facility: The UK strategy for intermediate level and certain low level radioactive waste disposal is based on production of cementitious waste-forms packaged in a standard range of containers as follows: 500 litre Drum - the normal container for most operational ILW (0.8 m diameter x 1.2 m high); 3 m"3 Box - a larger container for solid wastes (1.72 m x 1.72 m plan x 1.2 m high); 3 m"3 Drum - a larger container for in-drum mixing and immobilisation of sludge waste-forms (1.72 m diameter x 1.2 m high); 4 m Box - for large items of waste, especially from decommissioning (4.0 m x 2.4 m plan x 2.2 m high); 2 m LLW Box - for higher-density wastes (2.0 m x 2.4 m plan x 2.2 m high). In addition the majority of LLW is packaged by supercompaction followed by grouting in modified ISO freight containers (6 m x 2.5 m x 2.5 m). Some wastes do not fit easily into this strategy. These wastes include: very large items, (too big for the 4 m box) which, if dealt with whole, pose transport and disposal problems. These items are discussed further in Section 2; waste whose characteristics make packaging difficult. Such wastes are described in more detail in Section 3

Acceptance criteria for disposal of radioactive wastes in shallow ground and rock cavities

International Nuclear Information System (INIS)

1985-01-01

This document provides an overview of basic information related to waste acceptance criteria for disposal in shallow ground and rock cavity repositories, consisting of a discussion of acceptable waste types. The last item includes identification of those waste characteristics which may influence the performance of the disposal system and as such are areas of consideration for criteria development. The material is presented in a manner similar to a safety assessment. Waste acceptance criteria aimed at limiting the radiation exposure to acceptable levels are presented for each pathway. Radioactive wastes considered here are low-level radioactive wastes and intermediate-level radioactive wastes from nuclear fuel cycle operations and applications of radionuclides in research, medicine and industry

DOE acceptance of commercial mixed waste -- Studies are under way

Energy Technology Data Exchange (ETDEWEB)

Plummer, T.L. [Dept. of Energy, Washington, DC (United States). Technical Support Program; Owens, C.M. [Idaho National Engineering Lab., Idaho Falls, ID (United States). National Low-Level Waste Management Program

1993-03-01

The topic of the Department of Energy acceptance of commercial mixed waste at DOE facilities has been proposed by host States and compact regions that are developing low-level radioactive waste disposal facilities. States support the idea of DOE accepting commercial mixed waste because (a) very little commercial mixed waste is generated compared to generation by DOE facilities (Department of Energy--26,300 cubic meters annually vs. commercial--3400 cubic meters annually); (b) estimated costs for commercial disposal are estimated to be $15,000 to $40,000 per cubic foot; (c) once treatment capability becomes available, 70% of the current levels of commercial mixed waste will be eliminated, (d) some State laws prohibit the development of mixed waste disposal facilities in their States; (e) DOE is developing a nationwide strategy that will include treatment and disposal capacity for its own mixed waste and the incremental burden on the DOE facilities would be minuscule, and (6) no States are developing mixed waste disposal facilities. DOE senior management has repeatedly expressed willingness to consider investigating the feasibility of DOE accepting commercial mixed waste. In January 1991, Leo Duffy of the Department of energy met with members of the Low-Level Radioactive Waste Forum, which led to an agreement to explore such an arrangement. He stated that this seems like a cost-effective way to solve commercial mixed waste management problems.

Waste Management Strategies for Production of Mo-99

Energy Technology Data Exchange (ETDEWEB)

Cozzi, A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Johnson, F. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-01-31

Production of Mo-99 for medical isotope use is being investigated using dissolved low enriched uranium (LEU) fissioned using an accelerator driven process. With the production and separation of Mo-99, a low level waste stream will be generated. Since the production facility is a commercial endeavor, waste disposition paths normally available for federally generated radioactive waste may not be available. Disposal sites for commercially generated low level waste are available, and consideration to the waste acceptance criteria (WAC) of the disposal site should be integral in flowsheet development for the Mo-99 production. Pending implementation of the “Uranium Lease and Take-Back Program for Irradiation for Production of Molybdenum-99 for Medical Use” as directed by the American Medical Isotopes Production Act of 2012, there are limited options for disposing of the waste generated by the production of Mo-99 using an accelerator. The commission of a trade study to assist in the determination of the most favorable balance of production throughput and waste management should be undertaken. The use of a waste broker during initial operations of a facility has several benefits that can offset the cost associated with using a subcontractor. As the facility matures, the development of in-house capabilities can be expanded to incrementally reduce the dependence on a subcontractor.

HOW TO DEAL WITH WASTE ACCEPTANCE UNCERTAINTY USING THE WASTE ACCEPTANCE CRITERIA FORECASTING AND ANALYSIS CAPABILITY SYSTEM (WACFACS)

Energy Technology Data Exchange (ETDEWEB)

Redus, K. S.; Hampshire, G. J.; Patterson, J. E.; Perkins, A. B.

2002-02-25

The Waste Acceptance Criteria Forecasting and Analysis Capability System (WACFACS) is used to plan for, evaluate, and control the supply of approximately 1.8 million yd3 of low-level radioactive, TSCA, and RCRA hazardous wastes from over 60 environmental restoration projects between FY02 through FY10 to the Oak Ridge Environmental Management Waste Management Facility (EMWMF). WACFACS is a validated decision support tool that propagates uncertainties inherent in site-related contaminant characterization data, disposition volumes during EMWMF operations, and project schedules to quantitatively determine the confidence that risk-based performance standards are met. Trade-offs in schedule, volumes of waste lots, and allowable concentrations of contaminants are performed to optimize project waste disposition, regulatory compliance, and disposal cell management.

HOW TO DEAL WITH WASTE ACCEPTANCE UNCERTAINTY USING THE WASTE ACCEPTANCE CRITERIA FORECASTING AND ANALYSIS CAPABILITY SYSTEM (WACFACS)

International Nuclear Information System (INIS)

Redus, K. S.; Hampshire, G. J.; Patterson, J. E.; Perkins, A. B.

2002-01-01

The Waste Acceptance Criteria Forecasting and Analysis Capability System (WACFACS) is used to plan for, evaluate, and control the supply of approximately 1.8 million yd3 of low-level radioactive, TSCA, and RCRA hazardous wastes from over 60 environmental restoration projects between FY02 through FY10 to the Oak Ridge Environmental Management Waste Management Facility (EMWMF). WACFACS is a validated decision support tool that propagates uncertainties inherent in site-related contaminant characterization data, disposition volumes during EMWMF operations, and project schedules to quantitatively determine the confidence that risk-based performance standards are met. Trade-offs in schedule, volumes of waste lots, and allowable concentrations of contaminants are performed to optimize project waste disposition, regulatory compliance, and disposal cell management

Waste acceptance and waste loading for vitrified Oak Ridge tank waste

International Nuclear Information System (INIS)

Harbour, J.R.; Andrews, M.K.

1997-01-01

The Office of Science and Technology of the DOE has funded a joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC) to evaluate vitrification and grouting for the immobilization of sludge from ORNL tank farms. The radioactive waste is from the Gunite and Associated Tanks (GAAT), the Melton Valley Storage Tanks (MVST), the Bethel Valley Evaporator Service Tanks (BVEST), and the Old Hydrofractgure Tanks (OHF). Glass formulation development for sludge from these tanks is discussed in an accompanying article for this conference (Andrews and Workman). The sludges contain transuranic radionuclides at levels which will make the glass waste form (at reasonable waste loadings) TRU. Therefore, one of the objectives for this project was to ensure that the vitrified waste form could be disposed of at the Waste Isolation Pilot Plant (WIPP). In order to accomplish this, the waste form must meet the WIPP Waste Acceptance Criteria (WAC). An alternate pathway is to send the glass waste forms for disposal at the Nevada Test Site (NTS). A sludge waste loading in the feed of 6 wt percent will lead to a waste form which is non-TRU and could potentially be disposed of at NTS. The waste forms would then have to meet the requirements of the NTS WAC. This paper presents SRTC''s efforts at demonstrating that the glass waste form produced as a result of vitrification of ORNL sludge will meet all the criteria of the WIPP WAC or NTS WAC

Systematic handling of requirements and conditions (in compliance with waste acceptance requirements for a radioactive waste disposal facility)

International Nuclear Information System (INIS)

Keyser, Peter; Helander, Anita

2012-01-01

environment; iv) Aiding decision making on the authorization / licensing of radioactive waste disposal; and v) Facilitating communication amongst stakeholders on issues relating to the disposal facility. How can we ensure and control compliance with WAC during Pre-disposal activities? The link between the safety cases of Pre-disposal activities and the Disposal facility is primarily the Waste Acceptance Criteria (WAC), defined as 'those requirements that are to be met by conditioned radioactive wastes, forming packages, to be accepted at an Interim Storage or a Disposal Facility'. It is advised that also WAC should be set up for each stage of the pre-disposal activities in the Waste Management Plan or Strategy. Waste characterization requirements are typically developed from disposal performance assessment in addition to waste acceptance criteria (WAC), process control and quality assurance requirements, transportation requirements, and worker safety requirements. A matrix showing where each WAC originates can greatly assist with understanding the philosophy behind the overall characterization program and put the elements into context. The complexity of waste categorization requires the need for systematic handling of requirements and conditions during pre-disposal activities. How can we ensure the fulfillment of WAC for a radioactive waste disposal facility? Requirements management, sometimes called configuration management, is an area that recently has received increasing attention in the project management context. There exist international guidelines on the use of configuration management within an organization and it is applicable to the support of products from concept to disposal. It first outlines the responsibilities and authorities before describing the configuration management process that includes configuration management planning, configuration identification, change control, configuration status accounting and configuration audit. The methodology develops a

Environmental Restoration Disposal Facility Waste Acceptance Criteria

International Nuclear Information System (INIS)

Dronen, V.R.

1998-06-01

The Hanford Site is operated by the U. S. Department of Energy (DOE) with a primary mission of environmental cleanup and restoration. The Environmental Restoration Disposal Facility (ERDF) is an integral part of the DOE environmental restoration effort at the Hanford Site. The purpose of this document is to establish the ERDF waste acceptance criteria for disposal of materials resulting from Hanford Site cleanup activities. Definition of and compliance with the requirements of this document will enable implementation of appropriate measures to protect human health and the environment, ensure the integrity of the ERDF liner system, facilitate efficient use of the available space in the ERDF, and comply with applicable environmental regulations and DOE orders. To serve this purpose, the document defines responsibilities, identifies the waste acceptance process, and provides the primary acceptance criteria and regulatory citations to guide ERDF users. The information contained in this document is not intended to repeat or summarize the contents of all applicable regulations

Study of waste acceptance criteria for low-level radioactive waste from medical, industrial, and research facilities (Contract research)

International Nuclear Information System (INIS)

Koibuchi, Hiroto; Dohi, Terumi; Ishiguro, Hideharu; Hayashi, Masaru; Senda, Masaki

2008-12-01

Japan Atomic Energy Agency (JAEA) is supposed to draw up the plan for the disposal program of the very low-level radioactive waste and low-level radioactive waste generated from medical, industrial and research facilities. For instance, there are these facilities in JAEA, universities, private companies, and so on. JAEA has to get to know about the waste and its acceptance of other institutions described above because it is important for us to hold the licenses for the disposal program regarding safety assessment. This report presents the basic data concerning radioactive waste of research institutes etc. except RI waste, domestic and foreign information related to acceptance criteria for disposal of the low-level radioactive waste, the current status of foreign medical waste management, waste acceptance, and such. In this report, Japan's acceptance criteria were summarized on the basis of present regulation. And, the criteria of foreign countries, United States, France, United Kingdom and Spain, were investigated by survey of each reference. In addition, it was reported that the amount of waste from laboratories etc. for near-surface disposal and their characterization in our country. The Subjects of future work: the treatment of hazardous waste, the problem of the double-regulation (the Nuclear Reactor Regulation Law and the Law Concerning Prevention from Radiation Hazards due to Radioisotopes and Others) and the possession of waste were discussed here. (author)

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

DISPOSABLE CANISTER WASTE ACCEPTANCE CRITERIA

Energy Technology Data Exchange (ETDEWEB)

R.J. Garrett

2001-07-30

The purpose of this calculation is to provide the bases for defining the preclosure limits on radioactive material releases from radioactive waste forms to be received in disposable canisters at the Monitored Geologic Repository (MGR) at Yucca Mountain. Specifically, this calculation will provide the basis for criteria to be included in a forthcoming revision of the Waste Acceptance System Requirements Document (WASRD) that limits releases in terms of non-isotope-specific canister release dose-equivalent source terms. These criteria will be developed for the Department of Energy spent nuclear fuel (DSNF) standard canister, the Multicanister Overpack (MCO), the naval spent fuel canister, the High-Level Waste (HLW) canister, the plutonium can-in-canister, and the large Multipurpose Canister (MPC). The shippers of such canisters will be required to demonstrate that they meet these criteria before the canisters are accepted at the MGR. The Quality Assurance program is applicable to this calculation. The work reported in this document is part of the analysis of DSNF and is performed using procedure AP-3.124, Calculations. The work done for this analysis was evaluated according to procedure QAP-2-0, Control of Activities, which has been superseded by AP-2.21Q, Quality Determinations and Planning for Scientific, Engineering, and Regulatory Compliance Activities. This evaluation determined that such activities are subject to the requirements of DOE/RW/0333P, Quality Assurance Requirements and Description (DOE 2000). This work is also prepared in accordance with the development plan titled Design Basis Event Analyses on DOE SNF and Plutonium Can-In-Canister Waste Forms (CRWMS M&O 1999a) and Technical Work Plan For: Department of Energy Spent Nuclear Fuel Work Packages (CRWMS M&O 2000d). This calculation contains no electronic data applicable to any electronic data management system.

Public acceptance of radioactive waste transportation systems

International Nuclear Information System (INIS)

Gablin, K.A.

1978-01-01

As the thoughts of the country concentrate on the problems of transportation of waste through high traffic urban areas, the problem of how to deal directly and honestly with the public takes on greater significance in the nuclear industry. Non-technical aspects of the methods of transportation, especially by railroad and highway, enter into the total scheme of moving radioactive waste from both weapon and nuclear power plant sources to final processing and disposal. Factors such as shape, color, size, familiarity, and industrial designing are necessary ingredients that take on equal or more significance that the designing of containers to survive the hypothetical accident conditions of the present, or even of the future. Protective Packaging, Inc. has been a leader in the presentation of containers to the private and public sector of the nuclear industry. The products have undergone very open testing, in public, with both invited and uninvited witnesses. In those experiences, dating back to 1969, the problems of public acceptance will be related between the technical problems and the associated social and political problems that relate to container acceptance by the public in today's world. Proven experience data, relative to the safety of the present day systems will be discussed, as well as methods of improving the image in the future. Review will also be given to the effort by industry to discuss the proven record with parties outside the nuclear industry, i.e., individuals and pressure groups that are diametrically opposed to review the facts relative to safety as opposed to other, but more traditional industries

Arsenic in industrial waste water from copper production technological process

OpenAIRE

Biljana Jovanović; Milana Popović

2013-01-01

Investigation of arsenic in industrial waste water is of a great importance for environment. Discharge of untreated waste water from a copper production process results in serious pollution of surface water, which directly affects flora and fauna, as well as humans. There is a need for efficient and environmentally acceptable treament of waste waters containing heavy metals and arsenic. The paper presents an analyisis of the waste water from The Copper Smelter which is discharged into the Bor...

Physical system requirements - Accept waste

International Nuclear Information System (INIS)

1992-08-01

The Nuclear Waste Policy Act (NWPA) assigned to the Department of Energy (DOE) the responsibility for managing the disposal of spent nuclear fuel and high-level radioactive waste and established the Office of Civilian Radioactive Waste Management (OCRWM) for that purpose. The Secretary of Energy, in his November 1989 report to Congress (DOE/RW-0247), announced new initiatives for the conduct of the Civilian Radioactive Waste Management (CRWM) program. One of these initiatives was to establish improved management structure and procedures. In response, OCRWM performed a management study and the OCRWM Director subsequently issued the Management Systems improvement Strategy (MSIS) on August 10, 1990, calling for a rigorous implementation of systems engineering principles with a special emphasis on functional analysis. The functional analysis approach establishes a framework for integrating the program management efforts with the technical requirements analysis into a single, unified, and consistent program. This approach recognizes that just as the facilities and equipment comprising the physical waste management system must perform certain functions, so must certain programmatic and management functions be performed within the program in order to successfully bring the physical system into being. Thus, a comprehensive functional analysis effort has been undertaken which is intended to: Identify the functions that must be performed to fulfill the waste disposal mission; Identify the corresponding requirements imposed on each of the functions; and Identify the conceptual architecture that will be used to satisfy the requirements. The principal purpose of this requirements document is to present the results that were obtained from the conduct of a functional analysis effort for the Accept Waste mission

Documentation of acceptable knowledge for Los Alamos National Laboratory Plutonium Facility TRU waste stream

International Nuclear Information System (INIS)

Montoya, A.J.; Gruetzmacher, K.M.; Foxx, C.L.; Rogers, P.Z.

1998-03-01

Characterization of transuranic waste from the LANL Plutonium Facility for certification and transportation to WIPP includes the use of acceptable knowledge as specified in the WIPP Quality Assurance Program Plan. In accordance with a site specific procedure, documentation of acceptable knowledge for retrievably stored and currently generated transuranic waste streams is in progress at LANL. A summary overview of the TRU waste inventory is complete and documented in the Sampling Plan. This document also includes projected waste generation, facility missions, waste generation processes, flow diagrams, times, and material inputs. The second part of acceptable knowledge documentation consists of assembling more detailed acceptable knowledge information into auditable records and is expected to require several years to complete. These records for each waste stream must support final assignment of waste matrix parameters, EPA hazardous waste numbers, and radionuclide characterization. They must also include a determination whether waste streams are defense waste streams for compliance with the WIPP Land Withdrawal Act. The LANL Plutonium Facility's mission is primarily plutonium processing in basic special nuclear material (SNM) research activities to support national defense and energy programs. It currently has about 100 processes ranging from SNM recovery from residues to development of plutonium 238 heat sources for space applications. Its challenge is to characterize and certify waste streams from such diverse and dynamic operations using acceptable knowledge. This paper reports the progress on the certification of the first of these waste streams to the WIPP WAC

Characteristics of radioactive waste forms conditioned for storage and disposal: Guidance for the development of waste acceptance criteria

International Nuclear Information System (INIS)

1983-04-01

This report attempts to review the characteristics of the individual components of the waste package, i.e. the waste form and the container, in order to formulate, where appropriate, quidelines for the development of practical waste acceptance criteria. Primarily the criteria for disposal are considered, but if more stringent criteria are expected to be necessary for storage or transportation prior to the disposal, these will be discussed. The report will also suggest test areas which will aid the development of the final waste acceptance criteria

Gamma-ray spectrometry combined with acceptable knowledge (GSAK). A technique for characterization of certain remote-handled transuranic (RH-TRU) wastes. Part 1. Methodology and techniques

International Nuclear Information System (INIS)

Hartwell, J.K.; McIlwain, M.E.

2005-01-01

Gamma-ray spectrometry combined with acceptable knowledge (GSAK) is a technique for the characterization of certain remote-handled transuranic (RH-TRU) wastes. GSAK uses gamma-ray spectrometry to quantify a portion of the fission product inventory of RH-TRU wastes. These fission product results are then coupled with calculated inventories derived from acceptable process knowledge to characterize the radionuclide content of the assayed wastes. GSAK has been evaluated and tested through several test exercises. GSAK approach is described, while test results are presented in Part II. (author)

Acceptance criteria for radioactive waste deposition

International Nuclear Information System (INIS)

Rzyski, B.M.

1989-01-01

The disposal of low-and intermediate level radioactive waste in either shallow ground or rock cavities must be subjected to special guidelines which are used by national authorities and implementing bodies when establishing and regulating respositories. These informations are given by the acceptance criteria and will depend on specific site conditions and optmized procedures. (author) [pt

Management of radioactive waste from 99Mo production

International Nuclear Information System (INIS)

1998-11-01

99m Tc used for labelling different pharmaceuticals is the most important radionuclide in nuclear medicine practice, and probably will continue to play this important role for the foreseeable future. 99m Tc is the short lived daughter product of the parent 99 Mo, which is mainly produced by the nuclear fission of 235 U. Recognizing the importance of the waste management issue associated with 99 Mo production the IAEA initiated preparation of this report to provide Member States and existing and potential producers of 99 Mo with practical approaches and the available information on the subject. Waste management in the context of this report encompasses all waste-related aspects, for example, handling, treatment, conditioning, storage, transport, and disposal. The document is organized in several chapters giving the following information: short description of the basic nuclear and physical properties of 99 Mo and 99m Tc; an overview of past, present and possible future production methods; characteristics of the various waste streams produced in the aforementioned processes; description of the necessary waste management practices needed to handle the relevant waste streams in a responsible and internationally-accepted manner; conclusion and recommendations

Long-Term Safety Analysis of Baldone Radioactive Waste Repository and Updating of Waste Acceptance Criteria

International Nuclear Information System (INIS)

2001-12-01

The main objective of the project was to provide advice to the Latvian authorities on the safety enhancements and waste acceptance criteria for near surface radioactive waste disposal facilities of the Baldone repository. The project included the following main activities: Analysis of the current status of the management of radioactive waste in Latvia in general and, at the Baldone repository in particular Development of the short and long-term safety analysis of the Baldone repository, including: the planned increasing of capacity for disposal and long term storage, the radiological analysis for the post-closure period Development of the Environment Impact Statement, for the new foreseen installations, considering the non radiological components Proposal of recommendations for future updating of radioactive waste acceptance criteria Proposal of recommendations for safety upgrades to the facility. The work programme has been developed in phases and main tasks as follows. Phase 0: Project inception, Phase 1: Establishment of current status, plans and practices (Legislation, regulation and standards, Radioactive waste management, Waste acceptance criteria), Phase 2: Development of future strategies for long-term safety management and recommendations for safety enhancements. The project team found the general approach use at the installation, the basic design and the operating practices appropriate to international standards. Nevertheless, a number of items subject to potential improvements were also identified. These upgrading recommendations deal with general aspects of the management (mainly storage versus disposal of long-lived sources), site and environmental surveillance, packaging (qualification of containers, waste characterization requirements), the design of an engineered cap and strategies for capping. (author)

Waste Acceptance Decisions and Uncertainty Analysis at the Oak Ridge Environmental Management Waste Management Facility

International Nuclear Information System (INIS)

Redus, K. S.; Patterson, J. E.; Hampshire, G. L.; Perkins, A. B.

2003-01-01

The Waste Acceptance Criteria (WAC) Attainment Team (AT) routinely provides the U.S. Department of Energy (DOE) Oak Ridge Operations with Go/No-Go decisions associated with the disposition of over 1.8 million yd3 of low-level radioactive, TSCA, and RCRA hazardous waste. This supply of waste comes from 60+ environmental restoration projects over the next 15 years planned to be dispositioned at the Oak Ridge Environmental Management Waste Management Facility (EMWMF). The EMWMF WAC AT decision making process is accomplished in four ways: (1) ensure a clearly defined mission and timeframe for accomplishment is established, (2) provide an effective organization structure with trained personnel, (3) have in place a set of waste acceptance decisions and Data Quality Objectives (DQO) for which quantitative measures are required, and (4) use validated risk-based forecasting, decision support, and modeling/simulation tools. We provide a summary of WAC AT structure and performance. We offer suggestions based on lessons learned for effective transfer to other DOE

Waste Acceptance Decisions and Uncertainty Analysis at the Oak Ridge Environmental Management Waste Management Facility

Energy Technology Data Exchange (ETDEWEB)

Redus, K. S.; Patterson, J. E.; Hampshire, G. L.; Perkins, A. B.

2003-02-25

The Waste Acceptance Criteria (WAC) Attainment Team (AT) routinely provides the U.S. Department of Energy (DOE) Oak Ridge Operations with Go/No-Go decisions associated with the disposition of over 1.8 million yd3 of low-level radioactive, TSCA, and RCRA hazardous waste. This supply of waste comes from 60+ environmental restoration projects over the next 15 years planned to be dispositioned at the Oak Ridge Environmental Management Waste Management Facility (EMWMF). The EMWMF WAC AT decision making process is accomplished in four ways: (1) ensure a clearly defined mission and timeframe for accomplishment is established, (2) provide an effective organization structure with trained personnel, (3) have in place a set of waste acceptance decisions and Data Quality Objectives (DQO) for which quantitative measures are required, and (4) use validated risk-based forecasting, decision support, and modeling/simulation tools. We provide a summary of WAC AT structure and performance. We offer suggestions based on lessons learned for effective transfer to other DOE.

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)

Institutional innovation to generate the public acceptance of radioactive waste disposal

International Nuclear Information System (INIS)

Kemp, R.

1991-01-01

Contrasting experiences of public acceptance of radioactive waste disposal are compared for the United Kingdom, France, Sweden and Canada. The disparity between scientifically assessed and publicly perceived levels of risk is noted. The author argues that the form of decision-making process is more important to public acceptance of radioactive waste disposal than the technology of disposal. Public risk perception can be altered by procedures employed in planning, negotiation and consultation. Precisely what constitutes acceptable risk does vary from country to country, and differences in institutional responses and innovation are particularly highlighted. (UK)

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

International Nuclear Information System (INIS)

Gagner, L.; Voinis, S.

2000-01-01

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

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

International Nuclear Information System (INIS)

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

2012-01-01

Low and intermediate level radioactive waste must be sorted and treated before it can be sent to radioactive waste storage. The waste must fulfil an extensive amount of acceptance criteria (WAC) to guarantee a safe storage period. NUKEM Technologies has a broad experience with the building and management of radioactive waste treatment facilities and has developed methods and equipment to produce the waste packages and to gather all the required information. In this article we consider low and intermediate level radioactive waste excluding nuclear fuel material, even fresh fuel with low radiation. Only solid radioactive waste (RAW) will be considered. (Liquid RAW is usually processed and solidified before storage. Exception is the reprocessing of nuclear fuel.) Low and intermediate level radioactive waste has to be kept in storage facilities until isotopes are decayed sufficiently and the waste can be released. The storage has to fulfil certain conditions regarding the possible radiological impact and the possible chemical impact on the environment. With the inventory of nuclear waste characterised, the radiological impact can be estimated. RAW mainly originates from the operation of nuclear power plants. A small amount comes from reprocessing installations or from research entities. Chemical safety aspects are of qualitative nature, excluding substances in whole but not compared to limit values. Therefore they have minor influence on the storage conditions. Hereby corrosion and immobilisation of the waste play important roles. The storage concept assumes that the waste will be released if the radioactivity has decreased to an acceptable level. NUKEM Technologies has been specialised on collecting all data needed for the fulfilling of waste acceptance criteria (WAC). The classification as low or intermediate level waste is made on base of surface dose rate of the waste package as well as on the mass specific beta activity. Low level waste must not include isotopes

Gamma-ray spectrometry combined with acceptable knowledge (GSAK). A technique for characterization of certain remote-handled transuranic (RH-TRU) wastes. Part 2. Testing and results

International Nuclear Information System (INIS)

Hartwell, J.K.; McIlwain, M.E.

2005-01-01

Gamma-ray spectrometry combined with acceptable knowledge (GSAK) is a technique for the characterization of certain remote-handled transuranic (RH-TRU) wastes. GSAK uses gamma-ray spectrometry to quantify a portion of the fission product inventory of RH-TRU wastes. These fission product results are then coupled with calculated inventories derived from acceptable process knowledge to characterize the radionuclide content of the assayed wastes. GSAK has been evaluated and tested through several test exercises. These tests and their results are described; while the former paper in this issue presents the methodology, equipment and techniques. (author)

Baseline Glass Development for Combined Fission Products Waste Streams

International Nuclear Information System (INIS)

Crum, Jarrod V.; Billings, Amanda Y.; Lang, Jesse B.; Marra, James C.; Rodriguez, Carmen P.; Ryan, Joseph V.; Vienna, John D.

2009-01-01

Borosilicate glass was selected as the baseline technology for immobilization of the Cs/Sr/Ba/Rb (Cs), lanthanide (Ln) and transition metal fission product (TM) waste steams as part of a cost benefit analysis study.(1) Vitrification of the combined waste streams have several advantages, minimization of the number of waste forms, a proven technology, and similarity to waste forms currently accepted for repository disposal. A joint study was undertaken by Pacific Northwest National Laboratory (PNNL) and Savannah River National Laboratory (SRNL) to develop acceptable glasses for the combined Cs + Ln + TM waste streams (Option 1) and Cs + Ln combined waste streams (Option 2) generated by the AFCI UREX+ set of processes. This study is aimed to develop baseline glasses for both combined waste stream options and identify key waste components and their impact on waste loading. The elemental compositions of the four-corners study were used along with the available separations data to determine the effect of burnup, decay, and separations variability on estimated waste stream compositions.(2-5) Two different components/scenarios were identified that could limit waste loading of the combined Cs + LN + TM waste streams, where as the combined Cs + LN waste stream has no single component that is perceived to limit waste loading. Combined Cs + LN waste stream in a glass waste form will most likely be limited by heat due to the high activity of Cs and Sr isotopes.

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

International Nuclear Information System (INIS)

1990-03-01

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

WRAP low level waste restricted waste management (LLW RWM) glovebox acceptance test report

International Nuclear Information System (INIS)

Leist, K.J.

1997-01-01

On April 22, 1997, the Low Level Waste Restricted Waste Management (LLW RWM) glovebox was tested using acceptance test procedure 13027A-87. Mr. Robert L. Warmenhoven served as test director, Mr. Kendrick Leist acted as test operator and test witness, and Michael Lane provided miscellaneous software support. The primary focus of the glovebox acceptance test was to examine glovebox control system interlocks, operator Interface Unit (OIU) menus, alarms, and messages. Basic drum port and lift table control sequences were demonstrated. OIU menus, messages, and alarm sequences were examined, with few exceptions noted. Barcode testing was bypassed, due to the lack of installed equipment as well as the switch from basic reliance on fixed bar code readers to the enhanced use of portable bar code readers. Bar code testing was completed during performance of the LLW RWM OTP. Mechanical and control deficiencies were documented as Test Exceptions during performance of this Acceptance Test. These items are attached as Appendix A to this report

Management of radioactive waste in Belgium: ONDRAF/NIRAS and Belgoprocess as major actors of the waste acceptance system

International Nuclear Information System (INIS)

Zaelen, Gunter van; Verheyen, Annick

2007-01-01

The management of radioactive waste in Belgium is undertaken by the national agency for radioactive waste and enriched fissile materials, ONDRAF/NIRAS, and its industrial partner Belgoprocess. ONDRAF/NIRAS has set up a management system designed to guarantee that the general public and the environment are protected against the potential hazards arising from radioactive waste. Belgoprocess is a private company, founded in 1984 and located in Dessel, Belgium. It is a subsidiary of ONDRAF/NIRAS and its activities focus on the safe processing and storage of radioactive waste. The management system of ONDRAF/NIRAS includes two aspects: a) an integrated system and b) an acceptance system. The integrated system covers all aspects of management ranging from the origin of waste to its transport, processing, interim storage and long-term management. The safety of radioactive waste management not only depends on the quality of the design and construction of the processing, temporary storage or disposal infrastructure, but also on the quality of the waste accepted by ONDRAF/NIRAS. In order to be manage d safely, both in the short and the long term, the waste transferred to ONDRAF/NIRAS must meet certain specific requirements. To that end, ONDRAF/NIRAS has developed an acceptance system. (authors)

Public acceptance for centralized storage and repositories of low-level waste session (Panel)

Energy Technology Data Exchange (ETDEWEB)

Lutz, H.R.

1995-12-31

Participants from various parts of the world will provide a summary of their particular country`s approach to low-level waste management and the cost of public acceptance for low-level waste management facilities. Participants will discuss the number, geographic location, and type of low-level waste repositories and centralized storage facilities located in their countries. Each will discuss the amount, distribution, and duration of funds to gain public acceptance of these facilities. Participants will provide an estimated $/meter for centralized storage facilities and repositories. The panel will include a brief discussion about the ethical aspects of public acceptance costs, approaches for negotiating acceptance, and lessons learned in each country. The audience is invited to participate in the discussion.

Arsenic in industrial waste water from copper production technological process

Directory of Open Access Journals (Sweden)

Biljana Jovanović

2013-12-01

Full Text Available Investigation of arsenic in industrial waste water is of a great importance for environment. Discharge of untreated waste water from a copper production process results in serious pollution of surface water, which directly affects flora and fauna, as well as humans. There is a need for efficient and environmentally acceptable treament of waste waters containing heavy metals and arsenic. The paper presents an analyisis of the waste water from The Copper Smelter which is discharged into the Bor river. The expected arsenic content in treated waste water after using HDS procedure is also presented.

Chemical and radiological risk factors associated with waste from energy production

DEFF Research Database (Denmark)

Christensen, T.; Fuglestvedt, J.; Benestad, C.

1992-01-01

We have tried to estimate the toxic potential of waste from nuclear power plants and from power plants burning fossil fuels. The potential risks have been expressed as 'risk potentials' or 'person equivalents'. These are purely theoretical units and represent only an attempt to quantify...... and one has to accept a certain small risk by accepting the concentration limit. This is in line with the establishment of limits for radiation. Waste products from coal combustion have the highest potential risk among the fossil fuel alternatives. The highest risk is caused by metals, and the fly ash...... represents the effluent stream giving the largest contribution to the potential risk. The waste from nuclear power production has a lower potential risk than coal if today's limit values are used. If one adjusts the limits for radiation dose and the concentration limit values so that a similar risk...

Hanford Immobilized LAW Product Acceptance: Tanks Focus Area Testing Data Package II

International Nuclear Information System (INIS)

Schulz, Rebecca L.; Lorier, Troy H.; Peeler, David K.; Brown, Kevin G.; Reamer, Irene A.; Vienna, John D.; Jiricka, Antonin; Jorgensen, Benaiah M.; Smith, Donald E.

2001-01-01

This report is a continuation of the Hanford Immobilized Low Activity Waste (LAW) Product Acceptance (HLP): Initial Tanks Focus Area Testing Data Package (Vienna (and others) 2000). In addition to new 5000-h product consistency test (PCT), vapor hydration test (VHT), and alteration products data, some previously reported data together with relevant background information are included for an easily accessible source of reference when comparing the response of the various glasses to different test conditions. A matrix of 55 glasses was developed and tested to identify the impact of glass composition on long-term corrosion behavior and to develop an acceptable composition region for Hanford LAW glasses. Of the 55 glasses, 45 were designed to systematically vary the glass composition, and 10 were selected because large and growing databases on their corrosion characteristics had accumulated. The targeted and measured compositions of these glasses are found in the Appendix A. All glasses were fabricated according to standard procedures and heat treated to simulate the slow cooling that will occur in a portion of the waste glass after vitrification in the planned treatment facility at Hanford

Preliminary waste acceptance criteria for the ICPP spent fuel and waste management technology development program

International Nuclear Information System (INIS)

Taylor, L.L.; Shikashio, R.

1993-09-01

The purpose of this document is to identify requirements to be met by the Producer/Shipper of Spent Nuclear Fuel/High-LeveL Waste SNF/HLW in order for DOE to be able to accept the packaged materials. This includes defining both standard and nonstandard waste forms

Summary of research and development activities in support of waste acceptance criteria for WIPP

International Nuclear Information System (INIS)

Hunter, T.O.

1979-11-01

The development of waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP) is summarized. Specifications for acceptable waste forms are included. Nine program areas are discussed. They are: TRU characterization, HLW interactions, thermal/structural interactions, nuclide migration, permeability, brine migration, borehole plugging, operation/design support, and instrumentation development. Recommendations are included

Acceptance of failed SNF [spent nuclear fuel] assemblies by the Federal Waste Management System

International Nuclear Information System (INIS)

1990-03-01

This report is one of a series of eight prepared by E. R. Johnson Associates, Inc. (JAI) under ORNL's contract with DOE's OCRWM Systems Integration Program and in support of the Annual Capacity Report (ACR) Issue Resolution Process. The report topics relate specifically to the list of high priority technical waste acceptance issues developed jointly by DOE and a utility-working group. JAI performed various analyses and studies on each topic to serve as starting points for further discussion and analysis leading eventually to finalizing the process by which DOE will accept spent fuel and waste into its waste management system. The eight reports are concerned with the conditions under which spent fuel and high level waste will be accepted in the following categories: failed fuel; consolidated fuel and associated structural parts; non-fuel-assembly hardware; fuel in metal storage casks; fuel in multi-element sealed canisters; inspection and testing requirements for wastes; canister criteria; spent fuel selection for delivery; and defense and commercial high-level waste packages. This document discusses acceptance of failed spent fuel assemblies by the Federal Waste Management System. 18 refs., 7 figs., 25 tabs

TECHNO – ECONOMIC ACCEPTABILITY ANALISYS OF WASTE DISPOSAL BY INJECTION INTO APPROPRIATE FORMATION

Directory of Open Access Journals (Sweden)

Vladislav Brkić

2013-12-01

Full Text Available During exploration and production of oil and natural gas, various types of waste must be disposed in a permanent and safe way. There is a range of methods for processing and disposal of waste, such as disposal into landfills, solidification, namely chemical stabilization, thermal processing, appropriate formation injections uncovered by a deep well, disposal into salt domes and bioremediation. The method of waste disposal into appropriate formations is a method where strict geological and technical criteria must be satisfied when applied. A fundamental scientific hypothesis has been formulated whereby economic acceptability of the waste injection method, as a main method for waste disposal, is to be shown by an economic evaluation. The results of this research are relevant since there has been an intention in Croatia and worldwide to abandon wells permanently due to oil and gas reservoirs depletion and therefore it is essential to estimate economic impacts of the waste injection method application. In that way, profitability of using existing wells for waste disposal in oil industry has been increased, leading to the improvement of petroleum company’s business activities (the paper is published in Croatian.

Immobilisation of MTR waste in cement (product evaluation)

International Nuclear Information System (INIS)

Howard, C.G.; Lee, D.J.

1988-01-01

The enriched uranium/aluminium fuel used in Material Testing Reactors is reprocessed at Dounreay Nuclear Power Development Establishment (DNE). The main chemical component of the liquid waste produced by this process is acid deficient aluminium nitrate. The primary objective of this project is to find a suitable process for changing the highly mobile radioactive waste into an inert stable solid. Work carried out on the development of the immobilisation process showed that a conditioning stage (neutralisation) is required to make the acid waste compatible with cement. Small scale experiments showed that adding Ordinary Portland Cement blended with ground granulated Blast Furnace Slag to Simulant MTR Liquor produces an acceptable product. The process has been demonstrated at full scale (200 litres) and the products have been subjected to an extensive programme of destructive and non-destructive testing. (author)

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

International Nuclear Information System (INIS)

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

1998-05-01

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

Acceptance of waste for disposal in the potential United States repository at Yucca Mountain, Nevada

International Nuclear Information System (INIS)

Stahl, D.; Svinicki, K.

1996-01-01

This paper addresses the process for the acceptance of waste into the waste management system (WMS) with a focus on the detailed requirements identified from the Waste Acceptance System Requirements Document. Also described is the recent dialogue between OCRWM and the Office of Environmental Management to resolve issues, including the appropriate interpretation and application of regulatory and system requirements to DOE-owned spent fuel. Some information is provided on the design of the repository system to aid the reader in understanding how waste that is accepted into the WMS is received and emplaced in the repository

Acceptance criteria for disposal of radioactive waste in Romania

International Nuclear Information System (INIS)

Dogaru, D.

2001-01-01

In Romania the institutional radioactive waste are managed by National Institute of R and D for Physics and Nuclear Engineering. The institutional radioactive waste are collected, treated and conditioned at the Radioactive Waste Treatment Plant then transferred and disposed to the National Repository of Radioactive Waste at Baita Bihor. National Repository for Radioactive Waste is a long term storage facility. The repository is placed in a former worked out uranium ore mine, being excavated in the Bihor peak. The repository has been sited taking into account the known geological, hydrogeoloical, seismic and meteorological and mining properties of a uranium mining site. In the absence of an updated Safety Analysis Report, the maximum radioactive content permitted by the regulatory authority in the operation license is below the values reported for other engineered repositories in mine galleries. The paper presents the acceptance criteria for disposal of radioactive waste in National Repository for Radioactive Waste at Baita Bihor. (author)

Methods for verifying compliance with low-level radioactive waste acceptance criteria

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-09-01

This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility`s WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator`s waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits.

Methods for verifying compliance with low-level radioactive waste acceptance criteria

International Nuclear Information System (INIS)

1993-09-01

This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility's WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator's waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits

The role of weapons production and military waste in the repository selection process

International Nuclear Information System (INIS)

Nelson, D.; Hope, J.; Power, W.; Hunter, T.

1987-01-01

The decision to commingle defense waste with commercial waste in the nuclear waste repository program has many impacts on that program. There will be more waste to place in the two repositories authorized under the Nuclear Waste Policy Act, more transport miles to get the waste to a repository, and more costs associated with environmental and socio-economic impact mitigation. This paper explores the links between weapons production and military waste, and the repository selection process. The paper first describes the importance of state, tribe and public participation to the acceptance of a repository site selection. The paper then examines the various estimates of amounts of existing and future military nuclear wastes, and how these estimates affect repository siting decisions. The final section addresses the public policy questions which surround this issue. Repository siting may be jeopardized unless there is open public discussion about existing radioactive contamination at military production sites and about future nuclear weapons production. Cost-sharing is considered within this context

Risk analysis for new nuclear waste sites: Will it generate public acceptance?

International Nuclear Information System (INIS)

Inhaber, H.

1993-01-01

This report discusses public acceptance of radioactive waste facilities and what seems to be increasingly militant stances against such facilities. The role of risk assessment in possibly enhancing public acceptance is investigated

Reevaluating NIMBY: Evolving Public Fear and Acceptance in Siting a Nuclear Waste Facility

Energy Technology Data Exchange (ETDEWEB)

Jenkins-Smith, Hank C.; Silva, Carol L.; Nowlin, Matthew C.; deLozier, Grant (Dept. of Political Science, Univ. of Oklahoma, Norman, OK (United States))

2010-09-15

The not-in-my-backyard (NIMBY) syndrome has long been the focus of academic and policy research. We test several competing hypothesis concerning the sources of NIMBY sentiments, including demographics, proximity, political ideology and partisanship, and the unfolding policy process over time. To test these hypotheses we use survey data collected in New Mexico dealing with risk perceptions and acceptance related to the Waste Isolation Pilot Project (WIPP), a permanent storage site for radioactive waste located near Carlsbad, New Mexico. WIPP became operational and received its first shipment of waste on March 26, 1999. This study tracks the changes of risk perception and acceptance over a decade, using measures taken from 35 statewide surveys of New Mexico citizens spanning the 11-year period from fall 1990 to summer 2001. This time span includes periods before and after WIPP became operational. We find that acceptance of WIPP is greater among those in the most proximate counties to WIPP. Surprisingly, and contrary to expectations drawn from the broader literature, acceptance is also greater among those who live closest to the nuclear waste transportation route. We also find that ideology, partisanship, government approval and broader environmental concerns influence support for WIPP acceptance. Finally, the sequence of procedural steps taken toward formal approval of WIPP by government agencies proved to be important to public acceptance, the most significant being the opening of the WIPP facility itself

Reevaluating NIMBY: Evolving Public Fear and Acceptance in Siting a Nuclear Waste Facility

International Nuclear Information System (INIS)

Jenkins-Smith, Hank C.; Silva, Carol L.; Nowlin, Matthew C.; de Lozier, Grant

2010-09-01

The not-in-my-backyard (NIMBY) syndrome has long been the focus of academic and policy research. We test several competing hypothesis concerning the sources of NIMBY sentiments, including demographics, proximity, political ideology and partisanship, and the unfolding policy process over time. To test these hypotheses we use survey data collected in New Mexico dealing with risk perceptions and acceptance related to the Waste Isolation Pilot Project (WIPP), a permanent storage site for radioactive waste located near Carlsbad, New Mexico. WIPP became operational and received its first shipment of waste on March 26, 1999. This study tracks the changes of risk perception and acceptance over a decade, using measures taken from 35 statewide surveys of New Mexico citizens spanning the 11-year period from fall 1990 to summer 2001. This time span includes periods before and after WIPP became operational. We find that acceptance of WIPP is greater among those in the most proximate counties to WIPP. Surprisingly, and contrary to expectations drawn from the broader literature, acceptance is also greater among those who live closest to the nuclear waste transportation route. We also find that ideology, partisanship, government approval and broader environmental concerns influence support for WIPP acceptance. Finally, the sequence of procedural steps taken toward formal approval of WIPP by government agencies proved to be important to public acceptance, the most significant being the opening of the WIPP facility itself

Acceptance test plan for the Waste Information Control System

International Nuclear Information System (INIS)

Flynn, D.F.

1994-01-01

This document describes the acceptance test plan for the WICS system. The Westinghouse Hanford Company (WHC) Hazardous Material Control Group (HMC) of the 222-S Laboratory has requested the development of a system to help resolve many of the difficulties associated with tracking and data collection of containers and drums of waste. This system has been identified as Waste Information and Control System (WICS). The request for developing and implementing WICS has been made to the Automation and Simulation Engineering Group (ASE)

Does the choice of reactor affect public acceptance of wastes?

International Nuclear Information System (INIS)

Inhaber, H.

1993-01-01

A prime goal of this conference is to suggest future reactor types that would produce greater public acceptability. Presumably the wastes generated by these cycles would, because of lesser amounts or activities, engender fewer disputes over policy than in the past. However, the world-wide arguments over low-level wastes (LLW) suggest this intent is not likely to be achieved. While the activity of these wastes is a tiny fraction of high-level wastes (HLW), the controversies over the former, in Korea, the US and elsewhere, have been as great as for the latter. There is no linear relationship between activity and political desirability. What is needed is a new approach to disposing of and siting all nuclear wastes: LLW, mixed and HLW

A comparison and cross-reference of commercial low-level radioactive waste acceptance criteria

International Nuclear Information System (INIS)

Kerr, T.A.

1997-04-01

This document, prepared by the National Low-Level Waste Management Program at the Idaho National Engineering and Environmental Laboratory, is a comparison and cross-reference of commercial low-level radioactive waste acceptance criteria. Many of these are draft or preliminary criteria as well as implemented criteria at operating low-level radioactive waste management facilities. Waste acceptance criteria from the following entities are included: US Nuclear Regulatory Commission, South Carolina, Washington, Utah, Nevada, California, illinois, Texas, North Carolina, Nebraska, Pennsylvania, New York, and the Midwest Compact Region. Criteria in the matrix include the following: physical form, chemical form, liquid limits, void space in packages, concentration averaging, types of packaging, chelating agents, solidification media, stability requirements, sorptive media, gas, oil, biological waste, pyrophorics, source material, special nuclear material, package dimensions, incinerator ash, dewatered resin, transuranics, and mixed waste. Each criterion in the matrix is cross-referenced to its source document so that exact requirements can be determined

Preliminary Disposal Analysis for Selected Accelerator Production of Tritium Waste Streams

International Nuclear Information System (INIS)

Ades, M.J.; England, J.L.

1998-06-01

A preliminary analysis was performed for two selected Accelerator Production of Tritium (APT) generated mixed and low-level waste streams to determine if one mixed low-level waste (MLLW) stream that includes the Mixed Waste Lead (MWL) can be disposed of at the Nevada Test Site (NTS) and at the Hanford Site and if one low-level radioactive waste (LLW) stream, that includes the Tungsten waste stream (TWS) generated by the Tungsten Neutron Source modules and used in the Target/Blanket cavity vessel, can be disposed of in the LLW Vaults at the Savannah River Plant (SRP). The preliminary disposal analysis that the radionuclide concentrations of the two selected APT waste streams are not in full compliance with the Waste Acceptance Criteria (WAC) and the Performance Assessment (PA) radionuclide limits of the disposal sites considered

Analysis of local acceptance of a radioactive waste disposal facility.

Science.gov (United States)

Chung, Ji Bum; Kim, Hong-Kew; Rho, Sam Kew

2008-08-01

Like many other countries in the world, Korea has struggled to site a facility for radioactive waste for almost 30 years because of the strong opposition from local residents. Finally, in 2005, Gyeongju was established as the first Korean site for a radioactive waste facility. The objectives of this research are to verify Gyeongju citizens' average level of risk perception of a radioactive waste disposal facility as compared to other risks, and to explore the best model for predicting respondents' acceptance level using variables related to cost-benefit, risk perception, and political process. For this purpose, a survey is conducted among Gyeongju residents, the results of which are as follows. First, the local residents' risk perception of an accident in a radioactive waste disposal facility is ranked seventh among a total of 13 risks, which implies that nuclear-related risk is not perceived very highly by Gyeongju residents; however, its characteristics are still somewhat negative. Second, the comparative regression analyses show that the cost-benefit and political process models are more suitable for explaining the respondents' level of acceptance than the risk perception model. This may be the result of the current economic depression in Gyeongju, residents' familiarity with the nuclear industry, or cultural characteristics of risk tolerance.

Assessment of national systems for obtaining local acceptance of waste management siting and routing activities

Energy Technology Data Exchange (ETDEWEB)

Paige, H.W.; Lipman, D.S.; Owens, J.E.

1980-07-01

There is a rich mixture of formal and informal approaches being used in our sister nuclear democracies in their attempts to deal with the difficulties of obtaining local acceptance for siting of waste management facilities and activities. Some of these are meeting with a degree of success not yet achieved in the US. Although this survey documents and assesses many of these approaches, time did not permit addressing in any detail their relevance to common problems in the US. It would appear the US could benefit from a periodic review of the successes and failures of these efforts, including analysis of their applicability to the US system. Of those countries (Germany, Sweden, Switzerland, Japan, Belgium, and the US) who are working to a time table for the preparation of a high-level waste (HLW) repository, Germany is the only country to have gained local siting acceptance for theirs. With this (the most difficult of siting problems) behind them they appear to be in the best overall condition relative to waste management progress and plans. This has been achieved without a particularly favorable political structure, made up for by determination on the part of the political leadership. Of the remaining three countries studied (France, UK and Canada) France, with its AVM production facility, is clearly the world leader in the HLW immobilization aspect of waste management. France, Belgium and the UK appear to have the least favorable political structures and environments for arriving at waste management decisions. US, Switzerland and Canada appear to have the least favorable political structures and environments for arriving at waste management decisions.

HWVP compliance with the Hanford site solid waste acceptance criteria

International Nuclear Information System (INIS)

Bromm, R.; Ornelas, J.; Fundingsland, S.; Shah, K.

1993-01-01

In order to ensure that the Hanford Waste Vitrification Project (HWVP) will meet solid waste acceptance criteria, a review of the criteria was performed. The primary purpose of the study was to evaluate the modifications that will be required to bring the HWVP into compliance for secondary waste which will be generated during normal operations of the facility. To accomplish this objective, the current HWVP design was evaluated based on the criteria established. Once the non-compliance areas and potentially non-compliance areas were identified, alternative plant design modifications were proposed. This paper summarizes the results and recommendations of that study

Risk perception, risk evaluation and human values: cognitive bases of acceptability of a radioactive waste repository

International Nuclear Information System (INIS)

Earle, T.C.; Lindell, M.K.; Rankin, W.L.

1981-07-01

Public acceptance of radioactive waste management alternatives depends in part on public perception of the associated risks. Three aspects of those perceived risks were explored in this study: (1) synthetic measures of risk perception based on judgments of probability and consequences; (2) acceptability of hypothetical radioactive waste policies, and (3) effects of human values on risk perception. Both the work on synthetic measures of risk perception and on the acceptability of hypothetical policies included investigations of three categories of risk: (1) Short-term public risk (affecting persons living when the wastes are created), (2) Long-term public risk (affecting persons living after the time the wastes were created), and (3) Occupational risk (affecting persons working with the radioactive wastes). The human values work related to public risk perception in general, across categories of persons affected

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

Technology, socio-political acceptance, and the low-level radioactive waste disposal facility

International Nuclear Information System (INIS)

Andrews, L.J.; Domenech, J.S.

1986-01-01

The technology which is required to develop and operate low-level radioactive waste disposal sites in the 1990's is available today. The push for best available technology is a response to the political difficulties in securing public acceptance of the site selection process. Advances in waste management technologies include development of High Integrity Containers (HIC), solidification media, liquid volume reduction techniques using GEODE/sub sm/ and DeVoe-Holbein technology of selective removal of target radioisotopes, and CASTOR V storage casks. Advances in technology alone, however, do not make the site selection process easier and without socio-political acceptance there may be no process at all. Chem-Nuclear has been successful in achieving community acceptance at the Barnwell facility and elsewhere. For example, last June in Fall River County, South Dakota, citizens voted almost 2:1 to support the development of a low-level radioactive waste disposal facility. In Edgemont, the city nearest the proposed site, 85% of the voters were in favor of the proposed facility

Development of new waste form for treatment and disposal of concentrated liquid radioactive waste

International Nuclear Information System (INIS)

Kwak, Kyung Kil; Ji, Young Yong

2010-12-01

The radioactive waste form should be meet the waste acceptance criteria of national regulation and disposal site specification. We carried out a characterization of rad waste form, especially the characteristics of radioactivity, mechanical and physical-chemical properties in various rad waste forms. But asphalt products is not acceptable waste form at disposal site. Thus we are change the product materials. We select the development of the new process or new materials. The asphalt process is treatment of concentrated liquid and spent-resin and that we decide the Development of new waste form for treatment and disposal of concentrated liquid radioactive waste

Qualitative acceptance criteria for radioactive wastes to be disposed of in deep geological formations

International Nuclear Information System (INIS)

1990-05-01

The present Safety Guide has to be seen as a companion document to the IAEA Safety Series No. 99. It is concerned with the waste form which is an important component of the overall disposal system. Because of the broad range of waste types and conditioned forms and variations in the sites, designs and constructional approaches being considered for deep geological repositories, this report necessarily approaches the waste acceptance criteria in a general way, recognizing that the assignment of quantitative limits to these criteria has to be the responsibility of national authorities. The main objective of this Safety Guide is to set out qualitative waste acceptance criteria as a basis for specifying quantitative limits for the waste forms and packages which are intended to be disposed of in deep geological repositories. It should serve as guidance for assigning such parameter values which would fully comply with the safety assessment and performance of a waste disposal system as a whole. This document is intended to serve both national authorities and regulatory bodies involved in the development of deep underground disposal systems. The qualitative waste acceptance criteria dealt with in the present Safety Guide are primarily concerned with the disposal of high level, intermediate level and long-lived alpha bearing wastes in deep geological repositories. Although some criteria are also applicable in other waste disposal concepts, it has to be borne in mind that the set of criteria presented here shall ensure the isolation capability of a waste disposal system for periods of time much longer than for other waste streams with shorter lifetimes. 51 refs, 1 tab

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

Public perception and acceptance of the siting of nuclear waste facilities in seven countries

International Nuclear Information System (INIS)

Numark, N.J.; Paige, H.W.; Wonder, E.F.

1989-09-01

This report was prepared by ERC Environmental and Energy Services Co. (ERCE) on behalf of the Pacific Northwest Laboratory (PNL) and the US Department of Energy (DOE) between February and August 1989. It updates previous reports prepared by ERCE on public acceptance of waste management activities in foreign countries. The report is intended to serve as an aid in understanding experiences with public acceptance of waste activities in foreign countries, and thereby benefit US efforts with respect to public acceptance based on lessons learned abroad. Seven countries are addressed in the report: Belgium, the Federal Republic of Germany, France, Japan, Sweden, Switzerland, and the United Kingdom. The information provided in this report was obtained both from direct interviews of the responsible waste management officials in the seven countries surveyed and from source documents provided by these individuals

Risk perception, risk evaluation and human values: cognitive bases of acceptability of a radioactive waste repository

Energy Technology Data Exchange (ETDEWEB)

Earle, T.C.; Lindell, M.K.; Rankin, W.L.

1981-07-01

Public acceptance of radioactive waste management alternatives depends in part on public perception of the associated risks. Three aspects of those perceived risks were explored in this study: (1) synthetic measures of risk perception based on judgments of probability and consequences; (2) acceptability of hypothetical radioactive waste policies, and (3) effects of human values on risk perception. Both the work on synthetic measures of risk perception and on the acceptability of hypothetical policies included investigations of three categories of risk: (1) Short-term public risk (affecting persons living when the wastes are created), (2) Long-term public risk (affecting persons living after the time the wastes were created), and (3) Occupational risk (affecting persons working with the radioactive wastes). The human values work related to public risk perception in general, across categories of persons affected. Respondents were selected according to a purposive sampling strategy.

Reversing nuclear opposition: evolving public acceptance of a permanent nuclear waste disposal facility.

Science.gov (United States)

Jenkins-Smith, Hank C; Silva, Carol L; Nowlin, Matthew C; deLozier, Grant

2011-04-01

Nuclear facilities have long been seen as the top of the list of locally unwanted land uses (LULUs), with nuclear waste repositories generating the greatest opposition. Focusing on the case of the Waste Isolation Pilot Plant (WIPP) in southern New Mexico, we test competing hypotheses concerning the sources of opposition and support for siting the facility, including demographics, proximity, political ideology, and partisanship, and the unfolding policy process over time. This study tracks the changes of risk perception and acceptance of WIPP over a decade, using measures taken from 35 statewide surveys of New Mexico citizens spanning an 11-year period from fall 1990 to summer 2001. This time span includes periods before and after WIPP became operational. We find that acceptance of WIPP is greater among those whose residences are closest to the WIPP facility. Surprisingly, and contrary to expectations drawn from the broader literature, acceptance is also greater among those who live closest to the nuclear waste transportation route. We also find that ideology, partisanship, government approval, and broader environmental concerns influence support for WIPP acceptance. Finally, the sequence of procedural steps taken toward formal approval of WIPP by government agencies proved to be important to gaining public acceptance, the most significant being the opening of the WIPP facility itself. © 2010 Society for Risk Analysis.

DWPF waste glass Product Composition Control System

International Nuclear Information System (INIS)

Brown, K.G.; Postles, R.L.

1992-01-01

The Defense Waste Processing Facility (DWPF) will be used to blend aqueous radwaste (PHA) with solid radwaste (Sludge) in a waste receipt vessel (the SRAT). The resulting SRAT material is transferred to the SME an there blended with ground glass (Frit) to produce a batch of melter feed slurry. The SME material is passed to a hold tank (the MFT) which is used to continuously feed the DWPF melter. The melter. The melter produces a molten glass wasteform which is poured into stainless steel canisters for cooling and, ultimately, shipment to and storage in a geologic repository. The Product Composition Control System (PCCS) is the system intended to ensure that the melt will be processible and that the glass wasteform will be acceptable. This document provides a description of this system

Notice of inquiry on waste acceptance issues: Response summary

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-03-01

On May 25, 1994, the Department of Energy published a Notice of Inquiry on Waste Acceptance Issues in the Federal Register. Through this Notice of Inquiry, the Department sought to implement the Secretary`s initiative to explore with affected parties various options and methods for sharing the costs related to the financial burden associated with continued on-site storage by eliciting the views of affected parties on: (1) The Department`s preliminary view that it does not have a statutory obligation to begin accepting spent nuclear fuel in 1998 in the absence of an operational repository or other suitable storage facility constructed under the Nuclear Waste Policy Act of 1982, as amended; (2) The need for an interim, away-from-reactor storage facility prior to repository operations; and (3) Options for offsetting, through the Nuclear Waste Fund, a portion of the financial burden that may be incurred by utilities in continuing to store spent nuclear fuel at reactor sites beyond 1998. The Department received a total of 1,111 responses representing 1,476 signatories to this Notice of Inquiry. The responses included submittals from utilities (38 responses); public utility/service commissions and utility regulators (26 responses); Federal, state, and local governments, agencies, and representatives (23 responses); industry and companies (30 responses); public interest groups and other organizations (19 responses); and members of the general public (975 responses).

Notice of inquiry on waste acceptance issues: Response summary

International Nuclear Information System (INIS)

1995-03-01

On May 25, 1994, the Department of Energy published a Notice of Inquiry on Waste Acceptance Issues in the Federal Register. Through this Notice of Inquiry, the Department sought to implement the Secretary's initiative to explore with affected parties various options and methods for sharing the costs related to the financial burden associated with continued on-site storage by eliciting the views of affected parties on: (1) The Department's preliminary view that it does not have a statutory obligation to begin accepting spent nuclear fuel in 1998 in the absence of an operational repository or other suitable storage facility constructed under the Nuclear Waste Policy Act of 1982, as amended; (2) The need for an interim, away-from-reactor storage facility prior to repository operations; and (3) Options for offsetting, through the Nuclear Waste Fund, a portion of the financial burden that may be incurred by utilities in continuing to store spent nuclear fuel at reactor sites beyond 1998. The Department received a total of 1,111 responses representing 1,476 signatories to this Notice of Inquiry. The responses included submittals from utilities (38 responses); public utility/service commissions and utility regulators (26 responses); Federal, state, and local governments, agencies, and representatives (23 responses); industry and companies (30 responses); public interest groups and other organizations (19 responses); and members of the general public (975 responses)

Potential low-level waste disposal limits for activation products from fusion

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Peloquin, R.A.

1983-09-01

Hanford Engineering Development Laboratory (HEDL) scientists are involved in studies considering alternative construction materials for the first wall of commercial fusion reactors. To permit a comparison of radioactivity levels, both the level of activation and an acceptable limit for the radionuclides present must be known. Generic material composition guidelines can be developed using the US Nuclear Regulatory Commission (NRC) regulations governing the near-surface disposal of low-level radioactive wastes. These regulations consider wastes defined as containing source, special nuclear, or by-product materials arising from research, industrial, medical, and nuclear fuel-cycle activities. However, not all of the activation products produced in low-level wastes from fusion reactors are considered by the NRC in their regulations. The purpose of this report is to present potential low-level waste-disposal limits for ten radionuclides resulting from fusion reactor operations that are not considered in the NRC low-level waste regulations. These potential limits will be used by HEDL scientists to complete their generic material composition guidelines for the first wall of commercial fusion reactors

Remediation and production of low-sludge high-level waste glasses

International Nuclear Information System (INIS)

Ramsey, W.G.; Brown, K.G.; Beam, D.C.

1994-01-01

High-level radioactive sludge will constitute 24-28 oxide weight percent of the high-level waste glass produced at the Savannah River Site. A recent melter campaign using non-radioactive, simulated feed was performed with a sludge content considerably lower than 24 percent. The resulting glass was processed and shown to have acceptable durability. However, the durability was lower than predicted by the durability algorithm. Additional melter runs were performed to demonstrate that low sludge feed could be remediated by simply adding sludge oxides. The Product Composition Control System, a computer code developed to predict the proper feed composition for production of high-level waste glass, was utilized to determine the necessary chemical additions. The methodology used to calculate the needed feed additives, the effects of sludge oxides on glass production, and the resulting glass durability are discussed

Acceptance of spent nuclear fuel in multiple element sealed canisters by the Federal Waste Management System

International Nuclear Information System (INIS)

1990-03-01

This report is one of a series of eight prepared by E.R. Johnson Associates, Inc. (JAI) under ORNL's contract with DOE's OCRWM Systems Integration Program and in support of the Annual Capacity Report (ACR) Issue Resolution Process. The report topics relate specifically to the list of high priority technical waste acceptance issues developed jointly by DOE and a utility-working group. JAI performed various analyses and studies on each topic to serve as starting points for further discussion and analysis leading eventually to finalizing the process by which DOE will accept spent fuel and waste into its waste management system. The eight reports are concerned with the conditions under which spent fuel and high level waste will be accepted in the following categories: (1) failed fuel; (2) consolidated fuel and associated structural parts; (3) non-fuel-assembly hardware; (4) fuel in metal storage casks; (5) fuel in multi-element sealed canisters; (6) inspection and testing requirements for wastes; (7) canister criteria; (8) spent fuel selection for delivery; and (9) defense and commercial high-level waste packages. 14 refs., 27 figs

Aspects on the acceptance of waste for disposal in SFR

International Nuclear Information System (INIS)

Torstenfelt, Boerje

2006-01-01

When licensing a final repository for radioactive waste certain assumptions have to be made concerning the waste. These assumptions cover radionuclide inventory and nonradiological materials and its physical and chemical impact on the waste, the repository and on the environment. Development of new waste treatment systems and waste packages at the waste producer site aim at finding solutions and products that can be stored, transported and disposed of safely and are economically sound. This paper discusses some aspects concerning development of new or modified waste products. It highlights the importance of analysing the whole sequence in treatment, handling and disposing the waste. The process should be to find an optimal solution for the whole system, considering the fact that what is best in one step it not necessary best for the whole system, including the post closure issues. (author)

Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221F-HET/Drums

Energy Technology Data Exchange (ETDEWEB)

Lunsford, G.F.

1998-10-26

Since beginning operations in 1954, the Savannah River Site FB-Line produced Weapons Grade Plutonium for the United States National Defense Program. The facility mission was mainly to process dilute plutonium solution received from the 221-F Canyon into highly purified plutonium metal. As a result of various activities (maintenance, repair, clean up, etc.) in support of the mission, the facility generated a transuranic heterogeneous debris waste stream. Prior to January 25, 1990, the waste stream was considered suspect mixed transuranic waste (based on potential for inclusion of F-Listed solvent rags/wipes) and is not included in this characterization. Beginning January 25, 1990, Savannah River Site began segregation of rags and wipes containing F-Listed solvents thus creating a mixed transuranic waste stream and a non-mixed transuranic waste stream. This characterization addresses the non-mixed transuranic waste stream packaged in 55-gallon drums after January 25, 1990.Characterization of the waste stream was achieved using knowledge of process operations, facility safety basis documentation, facility specific waste management procedures and storage / disposal records. The report is fully responsive to the requirements of Section 4.0 "Acceptable Knowledge" from the WIPP Transuranic Waste Characterization Quality Assurance Plan, CAO-94-1010, and provides a sound, (and auditable) characterization that satisfies the WIPP criteria for Acceptable Knowledge.

Towards optimization of nuclear waste glass: Constraints, property models, and waste loading

International Nuclear Information System (INIS)

Hrma, P.

1994-04-01

Vitrification of both low- and high-level wastes from 177 tanks at Hanford poses a great challenge to glass makers, whose task is to formulate a system of glasses that are acceptable to the federal repository for disposal. The enormous quantity of the waste requires a glass product of the lowest possible volume. The incomplete knowledge of waste composition, its variability, and lack of an appropriate vitrification technology further complicates this difficult task. A simple relationship between the waste loading and the waste glass volume is presented and applied to the predominantly refractory (usually high-activity) and predominantly alkaline (usually low-activity) waste types. Three factors that limit waste loading are discussed, namely product acceptability, melter processing, and model validity. Glass formulation and optimization problems are identified and a broader approach to uncertainties is suggested

From waste to technology. An environmental acceptable technology

International Nuclear Information System (INIS)

Tabasaran, O.

2001-01-01

Modern thermal waste treatment has the task to produce deposit capable inert products and is able to reduce contaminants emitted to the environment. In addition waste to energy plants enable the recovery of energy by a maximum amount of environmental protection even in the comparison with modern power stations or other industrial plants. Over that, regarding modern technical solutions, today's waste to energy plants can no more be turned on financial reasons [it

Nuclear waste glass product consistency test (PCT): Version 7.0. Revision 3

International Nuclear Information System (INIS)

Jantzen, C.M.; Bibler, N.E.; Beam, D.C.; Ramsey, W.G.

1994-06-01

Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass will be produced in the Defense Waste Processing Facility (DWPF), poured into stainless steel canisters, and eventually disposed of in a geologic repository. In order to comply with the Waste Acceptance Product Specifications (WAPS), the durability of the glass needs to be measured during production to assure its long term stability and radionuclide release properties. A durability test, designated the Product Consistency Test (PCT), was developed for DWPF glass in order to meet the WAPS requirements. The response of the PCT procedure was based on extensive testing with glasses of widely different compositions. The PCT was determined to be very reproducible, to yield reliable results rapidly, and to be easily performed in shielded cell facilities with radioactive samples. Version 7.0 of the PCT procedure is attached. This draft version has been submitted to ASTM for full committee (C26, Nuclear Fuel Cycle) ballot after being balloted successfully through subcommittee C26.13 on Repository Waste Package Materials Testing

Central Waste Complex (CWC) Waste Analysis Plan

International Nuclear Information System (INIS)

ELLEFSON, M.D.

2000-01-01

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source special nuclear and by-product material components of mixed waste, radionuclides are not within the scope of this document. The information on radionuclides is provided only for general knowledge. This document has been revised to meet the interim status waste analysis plan requirements of Washington Administrative Code (WAC) 173 303-300(5). When the final status permit is issued, permit conditions will be incorporated and this document will be revised accordingly

Waste acceptance criteria study: Volume 2, Appendixes: Final report

International Nuclear Information System (INIS)

Johnson, E.R.; McLeod, N.B.; McBride, J.A.

1988-09-01

These appendices to the report on Waste Acceptance Criteria have been published as a separate volume for the convenience of the reader. They consist of the text of the 10CFR961 Contract for disposal of spent fuel, estimates of the cost (savings) to the DOE system of accepting different forms of spent fuel, estimates of costs of acceptance testing/inspection of spent fuel, illustrative specifications and procedures, and the resolution of comments received on a preliminary draft of the report. These estimates of costs contained herein preliminary and are intended only to demonstrate the trends in costs, the order of magnitude involved, and the methodology used to develop the costs. The illustrative specifications and procedures included herein have been developed for the purpose of providing a starting point for the development of a consensus on such matters between utilities and DOE

Statistical process control: An approach to quality assurance in the production of vitrified nuclear waste

International Nuclear Information System (INIS)

Pulsipher, B.A.; Kuhn, W.L.

1987-01-01

Current planning for liquid high-level nuclear wastes existing in the United States includes processing in a liquid-fed ceramic melter to incorporate it into a high-quality glass, and placement in a deep geologic repository. The nuclear waste vitrification process requires assurance of a quality product with little or no final inspection. Statistical process control (SPC) is a quantitative approach to one quality assurance aspect of vitrified nuclear waste. This method for monitoring and controlling a process in the presence of uncertainties provides a statistical basis for decisions concerning product quality improvement. Statistical process control is shown to be a feasible and beneficial tool to help the waste glass producers demonstrate that the vitrification process can be controlled sufficiently to produce an acceptable product. This quantitative aspect of quality assurance could be an effective means of establishing confidence in the claims to a quality product

Statistical process control: An approach to quality assurance in the production of vitrified nuclear waste

International Nuclear Information System (INIS)

Pulsipher, B.A.; Kuhn, W.L.

1987-02-01

Current planning for liquid high-level nuclear wastes existing in the US includes processing in a liquid-fed ceramic melter to incorporate it into a high-quality glass, and placement in a deep geologic repository. The nuclear waste vitrification process requires assurance of a quality product with little or no final inspection. Statistical process control (SPC) is a quantitative approach to one quality assurance aspect of vitrified nuclear waste. This method for monitoring and controlling a process in the presence of uncertainties provides a statistical basis for decisions concerning product quality improvement. Statistical process control is shown to be a feasible and beneficial tool to help the waste glass producers demonstrate that the vitrification process can be controlled sufficiently to produce an acceptable product. This quantitative aspect of quality assurance could be an effective means of establishing confidence in the claims to a quality product. 2 refs., 4 figs

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

Secondary Waste Cast Stone Waste Form Qualification Testing Plan

Energy Technology Data Exchange (ETDEWEB)

Westsik, Joseph H.; Serne, R. Jeffrey

2012-09-26

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

Quality control of radioactive waste products

International Nuclear Information System (INIS)

Martens, B.R.; Warnecke, E.; Odoj, R.

1986-01-01

The variety of incoming untreated wastes, treatment methods, waste forms and containers requires a great variety of controlling methods and principles to be applied both during waste treatment and on the final product. The paper describes product control schemes and methods, sampling systems and transportable testing equipment for waste drums, and equipment for waste cementation using in-drum stirring and subsequent fixation of solid wastes in the flowable product. (DG) [de

Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221F-HET/Drums

International Nuclear Information System (INIS)

Lunsford, G.F.

1999-01-01

This report is fully responsive to the requirements of Section 4.0 ''Acceptable Knowledge'' from the WIPP Transuranic Waste Characterization Quality Assurance Plan, CAO-94-1010, and provides a sound, (and auditable) characterization that satisfies the WIPP criteria for Acceptable Knowledge

Acceptable knowledge summary report for combustible/noncombustible, metallic, and HEPA filter waste resulting from 238Pu fabrication activities

International Nuclear Information System (INIS)

Rogers, P.S.Z.; Foxx, C.L.

1998-01-01

All transuranic (TRU) waste must be sufficiently characterized and certified before it is shipped to the Waste Isolation Pilot Plant (WIPP). The US Environmental Protection Agency (EPA) allows use of acceptable knowledge (AK) for waste characterization. EPA uses the term AK in its guidance document and defines AK and provides guidelines on how acceptable knowledge should be obtained and documented. This AK package has been prepared in accordance with Acceptable Knowledge Documentation (TWCP-QP-1.1-021,R.2). This report covers acceptable knowledge information for five waste streams generated at TA-55 during operations to fabricate various heat sources using feedstock 238 Pu supplied by the Savannah River Site (SRS). The 238 Pu feedstock itself does not contain quantities of RCRA-regulated constituents above regulatory threshold limits, as known from process knowledge at SRS and as confirmed by chemical analysis. No RCRA-regulated chemicals were used during 238 Pu fabrication activities at TA-55, and all 238 Pu activities were physically separated from other plutonium processing activities. Most of the waste generated from the 238 Pu fabrication activities is thus nonmixed waste, including waste streams TA-55-43, 45, and 47. The exceptions are waste streams TA-55-44, which contains discarded lead-lined rubber gloves used in the gloveboxes that contained the 238 Pu material, and TA-55-46, which may contain pieces of discarded lead. These waste streams have been denoted as mixed because of the presence of the lead-containing material

Review of palm oil fuel ash and ceramic waste in the production of concrete

Science.gov (United States)

Natasya Mazenan, Puteri; Sheikh Khalid, Faisal; Shahidan, Shahiron; Shamsuddin, Shamrul-mar

2017-11-01

High demand for cement in the concrete production has been increased which become the problems in the industry. Thus, this problem will increase the production cost of construction material and the demand for affordable houses. Moreover, the production of Portland cement leads to the release of a significant amount of CO2 and other gases leading to the effect on global warming. The need for a sustainable and green construction building material is required in the construction industry. Hence, this paper presents utilization of palm oil fuel ash and ceramic waste as partial cement replacement in the production of concrete. Using both of this waste in the concrete production would benefit in many ways. It is able to save cost and energy other than protecting the environment. In short, 20% usage of palm oil fuel ash and 30% replacement of ceramic waste as cement replacement show the acceptable and satisfactory strength of concrete.

Food waste and food processing waste for biohydrogen production: a review.

Science.gov (United States)

Yasin, Nazlina Haiza Mohd; Mumtaz, Tabassum; Hassan, Mohd Ali; Abd Rahman, Nor'Aini

2013-11-30

Food waste and food processing wastes which are abundant in nature and rich in carbon content can be attractive renewable substrates for sustainable biohydrogen production due to wide economic prospects in industries. Many studies utilizing common food wastes such as dining hall or restaurant waste and wastes generated from food processing industries have shown good percentages of hydrogen in gas composition, production yield and rate. The carbon composition in food waste also plays a crucial role in determining high biohydrogen yield. Physicochemical factors such as pre-treatment to seed culture, pH, temperature (mesophilic/thermophilic) and etc. are also important to ensure the dominance of hydrogen-producing bacteria in dark fermentation. This review demonstrates the potential of food waste and food processing waste for biohydrogen production and provides a brief overview of several physicochemical factors that affect biohydrogen production in dark fermentation. The economic viability of biohydrogen production from food waste is also discussed. Copyright © 2013 Elsevier Ltd. All rights reserved.

Radioactive waste products 2002 (RADWAP 2002). Proceedings

International Nuclear Information System (INIS)

Odoj, R.; Baier, J.; Brennecke, P.; Kuehn, K.

2003-01-01

The 4 th International Seminar on Radioactive Waste Products was organised by the Forschungszentrum Juelich in co-operation with the Bundesamt fuer Strahlenschutz and the European Commission. On behalf of the Bundesamt, I would like to welcome all participants of this scientific-technical meeting. I very much appreciate the participation not only of numerous German scientists, engineers and technicians as well as governmental and industrial representatives, but would particularly express my gratitude for the participation of many colleagues from abroad. Radioactive waste management and disposal is a worldwide issue and international co-operation to support national programmes is therefore much appreciated. The international organisations provide, among other things, guidance to member countries on safe, economic and environmentally acceptable solutions for radioactive waste disposal. On a national basis respective programmes are developed, modified or successfully realized. Nevertheless, the challenge of radioactive waste management and disposal is no longer a scientific and technical exclusivity. The importance of ethical and social aspects, the dialogue with the public and transparency in decision-making processes increase more and more. Thus, when addressing safety-related key questions one needs to be as open as possible on scientific-technical aspects and to consider the involvement of the public requiring a clear, open-minded and transparent communication. (orig.)

Development of Waste Acceptance Criteria at 221-U Building: Initial Flow and Transport Scoping Calculations

Energy Technology Data Exchange (ETDEWEB)

Freedman, Vicky L.; Zhang, Z. F.; Keller, Jason M.; Chen, Yousu

2007-05-30

This report documents numerical flow and transport simulations performed that establish initial waste acceptance criteria for the potential waste streams that may be safely sequestered in the 221-U Building and similar canyon structures. Specifically, simulations were executed to identify the maximum loading of contaminant mass (without respect to volume) that can be emplaced within the 221-U Building with no more than 1 pCi/m2 of contaminant migrating outside the structure within a 1,000 year time period. The initial scoping simulations were executed in one dimension to assess important processes, and then two dimensions to establish waste acceptance criteria. Two monolithic conditions were assessed: (1) a grouted canyon monolith; and (2) a canyon monolith filled with sand, both assuming no cracks or fissures were present to cause preferential transport. A three-staged approach was taken to account for different processes that may impact the amount of contaminant that can be safely sequestered in canyon structure. In the first stage, flow and transport simulations established waste acceptance criteria based on a linear (Kd) isotherm approach. In the second stage, impacts on thermal loading were examined and the differences in waste acceptance criteria quantified. In the third stage of modeling, precipitation/dissolution reactions were considered on the release and transport of the contaminants, and the subsequent impact on the maximum contaminant loading. The reactive transport modeling is considered a demonstration of the reactive transport capability, and shows the importance of its use for future performance predictions once site-specific data have been obtained.

Secondary Waste Form Screening Test Results—THOR® Fluidized Bed Steam Reforming Product in a Geopolymer Matrix

Energy Technology Data Exchange (ETDEWEB)

Pires, Richard P.; Westsik, Joseph H.; Serne, R. Jeffrey; Mattigod, Shas V.; Golovich, Elizabeth C.; Valenta, Michelle M.; Parker, Kent E.

2011-07-14

Screening tests are being conducted to evaluate waste forms for immobilizing secondary liquid wastes from the Hanford Tank Waste Treatment and Immobilization Plant (WTP). Plans are underway to add a stabilization treatment unit to the Effluent Treatment Facility to provide the needed capacity for treating these wastes from WTP. The current baseline is to use a Cast Stone cementitious waste form to solidify the wastes. Through a literature survey, DuraLith alkali-aluminosilicate geopolymer, fluidized-bed steam reformation (FBSR) granular product encapsulated in a geopolymer matrix, and a Ceramicrete phosphate-bonded ceramic were identified both as candidate waste forms and alternatives to the baseline. These waste forms have been shown to meet waste disposal acceptance criteria, including compressive strength and universal treatment standards for Resource Conservation and Recovery Act (RCRA) metals (as measured by the toxicity characteristic leaching procedure [TCLP]). Thus, these non-cementitious waste forms should also be acceptable for land disposal. Information is needed on all four waste forms with respect to their capability to minimize the release of technetium. Technetium is a radionuclide predicted to be in the secondary liquid wastes in small quantities, but the Integrated Disposal Facility (IDF) risk assessment analyses show that technetium, even at low mass, produces the largest contribution to the estimated IDF disposal impacts to groundwater.

Waste Analysis Plan for the Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

TRINER, G.C.

1999-01-01

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for dangerous, mixed, and radioactive waste accepted for confirmation, nondestructive examination (NDE) and nondestructive assay (NDA), repackaging, certification, and/or storage at the Waste Receiving and Processing Facility (WRAP). Mixed and/or radioactive waste is treated at WRAP. WRAP is located in the 200 West Area of the Hanford Facility, Richland, Washington. 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

Preliminary assessment of nine waste-form products/processes for immobilizing transuranic wastes

International Nuclear Information System (INIS)

Crisler, L.R.

1980-09-01

Nine waste-form processes for reduction of the present and projected Transuranic (TRU) waste inventory to an immobilized product have been evaluated. Product formulations, selected properties, preparation methods, technology status, problem areas needing resolution and location of current research development being pursued in the United States are discussed for each process. No definitive utility ranking is attempted due to the early stage of product/process development for TRU waste containing products and the uncertainties in the state of current knowledge of TRU waste feed compositional and quantitative makeup. Of the nine waste form products/processes included in this discussion, bitumen and cements (encapsulation agents) demonstrate the degree of flexibility necessary to immobilize the wide composition range present in the TRU waste inventory. A demonstrated process called Slagging Pyrolysis Incineration converts a varied compositional feed (municipal wastes) to a ''basalt'' like product. This process/product appears to have potential for TRU waste immobilization. The remaining waste forms (borosilicate glass, high-silica glass, glass ceramics, ''SYNROC B'' and cermets) have potential for immobilizing a smaller fraction of the TRU waste inventory than the above discussed waste forms

Special Analysis for the Disposal of the Neutron Products Incorporated Sealed Source Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

Energy Technology Data Exchange (ETDEWEB)

None, None

2014-08-31

The purpose of this special analysis (SA) is to determine if the Neutron Products Incorporated (NPI) Sealed Sources waste stream (DRTK000000056, Revision 0) is suitable for disposal by shallow land burial (SLB) at the Area 5 Radioactive Waste Management Site (RWMS). The NPI Sealed Sources waste stream consists of 850 60Co sealed sources (Duratek [DRTK] 2013). The NPI Sealed Sources waste stream requires a special analysis (SA) because the waste stream 60Co activity concentration exceeds the Nevada National Security Site (NNSS) Waste Acceptance Criteria (WAC) Action Levels.

Review of issues relevant to acceptable risk criteria for nuclear waste management

International Nuclear Information System (INIS)

Cohen, J.J.

1978-01-01

Development of acceptable risk criteria for nuclear waste management requires the translation of publicly determined goals and objectives into definitive issues which, in turn, require resolution. Since these issues are largely of a subjective nature, they cannot be resolved by technological methods. Development of acceptable risk criteria might best be accomplished by application of a systematic methodology for the optimal implementation of subjective values. Multi-attribute decision analysis is well suited for this purpose

Beneficial utilization of nuclear waste products

International Nuclear Information System (INIS)

Dix, G.P.

1975-01-01

A sufficient supply of isotopes exists to conduct demonstrational experiments in the 1975-1980 time frame to stimulate a market for waste products. A large potential market exists for a number of waste products, measured in terms of billions of dollars. Actinide by-products can become a feed stock for producing other energy producing isotopes by neutron irradiation whose value may exceed that of the fission products. Commercial reprocessors will not invest in the extraction and separation of isotopes from the waste stream until a proven market has evolved. Economic studies must be performed to establish the trade-offs between the beneficial use or disposal of wastes. Fundamental to these studies are process economics, safety analyses applications studies, and market analyses, both domestic and foreign. Regardless of the degree of beneficial utilization of wastes, some residual material from wastes not utilized and spent by-products after utilization will have to undergo ultimate disposal. Isotopic waste products have the potential for solving a number of societal and national security problems and represent a unique source of energy and materials

Conceptual and economic foundations of strategic management of solid waste products

Directory of Open Access Journals (Sweden)

Leyla Borisovna Leonova

2015-11-01

Full Text Available The article reviews existing global concept in the field of waste production and consumption.The purpose of this investigation is the development of a new hierarchy of waste mana-gement and adjustment of the existing waste management strategy, acceptable to Russia. To analyze the current situation of waste production and consumption there was studied foreign experience in waste management and considered the situation of waste in the Russian Federation and Sverdlovsk region. Analytical, statistical and theoretical methods of work were used.The new hierarchy of desirable waste management is based on the following order: selective collection of waste, particularly household, their recycling and thereby minimize them, and then their treatment and further disposal. This new hierarchy will significantly reduce the burden on the environment and land resources.The revised strategy for solid waste management should consist of 6 blocks, ranked in a logical sequence: organizational, legal, science and research, economic, controlling, educational. Each of them includes a list of activities. Term strategy implementation is 5 years, followed by a possible prolongation.To improve the efficiency of work in the field of solid waste management in Russia must be created a new waste recycling industry, which can be provided by necessary infrastructure for the collection, transportation, recycling and disposal of solid waste products. It is also required to monitor environmental pollution waste using geographic information systems and provide educational work among population and the leaders of the industrial and communal enterprises.In the article in addition to the world concept the authors took into account an economic component, which includes analysis of the costs of environmental protection measures and economic damage caused by waste disposal. The paper also provides an industry deformed structure of the Russian economy, which explains the inability to

Product Control of Waste Products with New Coating Materials

International Nuclear Information System (INIS)

Krumbach, H.; Steinmetz, H.J.; Odoj, R.; Wartenberg, W.; Grunau, H.

2009-01-01

In Germany, with the shaft KONRAD a repository for low radioactive waste will be available at the earliest in the year 2013. The previously conditioned radioactive waste has to be suitable for a longer-term interim storage. They have to be treated in a way that they are chemically stable and that their integrity is guaranteed for a long time. That is why the waste product or the container is covered/ coated for special waste such as hygroscopic waste or waste that includes aluminium. The Product Control Group for radioactive waste (PKS) has to proof the suitability of the so-treated waste for the repository KONRAD on behalf of the Federal Office for Radiation Protection (BfS). This has to be done before the delivering. In this context the PKS also assesses the suitability of new coating materials for low radioactive waste products or containers and their correct technical application. The characteristics and the technical application of polyurethane coatings as well as the control of the so-coated waste for the disposal in the shaft KONRAD are described in this poster. The Poster shows the development stages of the coating and the filling. There are also shown the boundary conditions and the investigations of the Product Control Group for the use of the new coating material for radioactive waste. (authors)

The role of waste package specifications as a forerunner to ILW repository conditions for acceptance

International Nuclear Information System (INIS)

Barlow, S.V.; Palmer, J.D.

1998-01-01

In the absence of a finalized repository site, design or associated safety case, Nirex is not in a position to issue conditions for acceptance. Nirex has therefore developed a strategy which facilitates packaging of intermediate level waste by providing guidance through waste package specifications, supported by the formal assessment of specific packaging proposals on a case-by-case basis. The waste package specifications are comprehensive and cover all aspects of the waste package including dimensions and other key features, performance standards, wasteform, quality assurance, and data recording requirements. The waste package specifications will be subject to periodic review as repository design and safety cases are finalized and will progressively become site- and design-specific. The waste package specifications will eventually form the basis for conditions for acceptance. The strategy described in this paper has been successfully followed by Nirex and customers for the past ten years and has permitted wastes to be packaged for a deep repository with confidence in the absence of a finalized site and safety cases for the repository. Because the process has its basis in a generic repository concept, it remains robust, despite the increased uncertainty following the March 1997 Secretary of State's decision, as to the siting and time-scale of a deep waste repository, and continues to be an important component of the UK's waste management strategy. (author)

Waste vitrification: prediction of acceptable compositions in a lime-soda-silica glass-forming system

International Nuclear Information System (INIS)

Gilliam, T.M.; Jantzen, C.M.

1996-10-01

A model is presented based upon calculated bridging oxygens which allows the prediction of the region of acceptable glass compositions for a lime-soda-silica glass-forming system containing mixed waste. The model can be used to guide glass formulation studies (e.g., treatability studies) or assess the applicability of vitrification to candidate waste streams

Acceptance criteria considerations for miscellaneous wastes

International Nuclear Information System (INIS)

Irvine, A.R.; Forsberg, C.W.

1987-01-01

EPA standards set forth limitations regarding releases to the accessible environment adjacent to a geologic repository. The NRC criteria pertaining to waste form and engineered barrier performance place certain restrictions on the physical and chemical nature of the waste form and require substantially complete confinement of radioactivity until the high-heat-production period is past. After this period, the annual release of radionuclides from the waste package is normally limited to 1 part in 100,000 of the amounts calculated to be present at 1000-y decay. The regulation permits deviation from these criteria in exceptional circumstances. One such circumstance might be the absence of a significant perturbation in temperature around the stored waste. The lack of significant heat release will eliminate the hydrologic driving force for dispersal of radionuclides. Exceptional circumstances which potentially could justify a less stringent long-term release criterion are: small quantity of radioactivity, the nature of the radioactive species, and the nature of the geology in which the waste is to be emplaced. Because the MW after a suitable decay period have low heat release rates per unit volume, they apparently could be so emplaced in a repository that there would be no compelling need, according to the reasoning presented in 10 CFR 60, for a 1000-y container. Regarding attainment of the specified long-term release rate criterion, neither the solubility limits for the various waste forms nor the conductance of potential migration barriers are currently adequately characterized. The relatively small total heat generation rate for the MW in combination with the usual low volumetric heat generation rate apparently will allow application of migration barriers in a low temperature environment where barrier performance would be expected to be unchanged with time

Waste management: products and services

International Nuclear Information System (INIS)

Anon.

1992-01-01

A number of products and services related to radioactive waste management are described. These include: a portable cement solidification system for waste immobilization; spent fuel storage racks; storage and transport flasks; an on-site low-level waste storage facility; supercompactors; a mobile waste retrieval and encapsulation plant; underwater crushers; fuel assembly disposal; gaseous waste management; environmental restoration and waste management services; a waste treatment consultancy. (UK)

Product specific emissions from municipal solid waste landfills

DEFF Research Database (Denmark)

Nielsen, Per Henning; Exner, Stephan; Jørgensen, Anne-Mette

1998-01-01

This paper presents and verifies the computer tool LCA-LAND for estimation of emissions from specific waste products disposed in municipal solid waste landfills in European countries for use in the inventory analysis of LCA. Examples of input data (e.g. distribution of the waste product...... in different countries, composition of the product and physical/chemical/biological properties of waste product components) and output data (e.g. estimated emissions to atmosphere and water) are given for a fictive waste product made of representative types of components (toluene, cellulose, polyvinylchloride...... (PVC), copper and chloride). Since waste products from different processes in the product system may be disposed at different landfills where they are mixed with waste originating outside the product system, the estimated emissions from specific waste products cannot be compared with measured emissions...

Production controls (PC) and technical verification testing (TVT). A methodology for the control and tracking of LILW waste package conditioning

International Nuclear Information System (INIS)

Leon, A.M.; Nieto, J.L.L.; Garrido, J.G.

2003-01-01

As part of its low and intermediate level radioactive waste (LILW) characterisation and acceptance activities, ENRESA has set up a quality control programme that covers the different phases of radioactive waste package production and implies different levels of tracking in generation, assessment of activity and control of the documentation associated therewith. Furthermore, ENRESA has made available the mechanisms required for verification, depending on the results of periodic sampling, of the quality of the end product delivered by the waste producers. Both processes are included within the framework of two programmes of complementary activities: production controls (PC) and technical verification testing (TVT). (orig.)

Acceptability of a low and intermediate level radioactive waste repository

International Nuclear Information System (INIS)

Zeleznik, N.; Polic, M.

2000-01-01

Siting of a radioactive waste repository, even for the waste of low and intermediate level (LILW) radioactivity, presents a great problem in almost every country that produces such waste. The main problem is not a technical one, but socio-psychological, namely the acceptability of this kind of repository. In general, people are opposed to any such kind of facility in their vicinity (NIMBY). In this study we try to establish the factors that influence people's behavior regarding the construction of a radioactive waste repository in their local community, with the use of Ajzen's model of planned behavior. Two different scenarios about the construction of a radioactive waste repository in their community, together with a set of questions were presented to participants from different schools. Data from the survey were analysed by multivariate methods, and a model of relevant behaviour was proposed. From the results it can be seen that different approaches to local community participation in site selection process slightly influence people's attitudes towards the LILW repository, while significant differences in answers were found in the responses which depend on participants' knowledge. Therefore the RAO Agency will further intensify preparation of the relevant communication plan and start with its implementation to support LILW repository site selection process, which will also include educational programme. (author)

Nuclear waste glass product consistency test (PCT), Version 5.0

International Nuclear Information System (INIS)

Jantzen, C.M.; Bibler, N.E.; Beam, D.C.; Ramsey, W.G.; Waters, B.J.

1992-06-01

Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass will be produced in the Defense Waste Processing Facility (DWPF), poured into stainless steel canisters, and eventually disposed of in a geologic repository. In order to comply with the Waste Acceptance Preliminary Specifications (WAPS), the durability of the glass needs to be measured during production to assure its long term stability and radionuclide release properties. A durability test, designated the Produce Consistency Test (PCT), was developed for DWPF glass in order to meet the WAPS requirements. The response of the PCT procedure was based on extensive testing with glasses of widely different compositions. The PCT was determined to be very reproducible, to yield reliable results rapidly, and to be easily performed in shielded cell facilities with radioactive samples. Version 5.0 of the PCT procedure is attached

Special Analysis: Updated Analysis of the Effect of Wood Products on Trench Disposal Limits at the E-Area Low-Level Waste Facility

International Nuclear Information System (INIS)

Cook, J.R.

2001-01-01

This Special Analysis (SA) develops revised radionuclide inventory limits for trench disposal of low-level radioactive waste in the presence of wood products in the E-Area Low-Level Waste Facility. These limits should be used to modify the Waste Acceptance Criteria (WAC) for trench disposal. Because the work on which this SA is based employed data from tests using 100 percent wood products, the 40 percent limitation on wood products for trench (i.e., slit or engineered trench) disposal is not needed in the modified WAC

Inspection method for solidification product of radioactive waste and method of preparing solidification product of radiation waste

International Nuclear Information System (INIS)

Izumida, Tatsuo; Tamada, Shin; Matsuda, Masami; Kamata, Shoji; Kikuchi, Makoto.

1993-01-01

A powerful X-ray generation device using an electron-ray accelerator is used for inspecting presence or absence of inner voids in solidification products of radioactive wastes during or after solidification. By installing the X-ray CT system and the radioactive waste solidifying facility together, CT imaging for solidification products is conducted in a not-yet cured state of solidifying materials during or just after the injection. If a defect that deteriorates the durability of the solidification products should be detected, the solidification products are repaired, for example, by applying vibrations to the not-yet cured solidification products. Thus, since voids or cracks in the radioactive wastes solidification products, which were difficult to be measured so far, can be measured in a short period of time accurately thereby enabling to judge adaptability to the disposal standards, inspection cost for the radioactive waste solidification product can be saved remarkably. Further, the inside of the radioactive waste solidification products can be evaluated correctly and visually, so that safety in the ground disposal storage of the radioactive solidification products can be improved remarkably. (N.H.)

Acceptability criteria for final underground disposal of radioactive waste

International Nuclear Information System (INIS)

Sousselier, Y.

1984-01-01

Specialists now generally agree that the underground disposal of suitably immobilized radioactive waste offers a means of attaining the basic objective of ensuring the immediate and long-term protection of man and the environment throughout the requisite period of time and in all foreseeable circumstances. Criteria of a more general as well as a more specific nature are practical means through which this basic protection objective can be reached. These criteria, which need not necessarily be quantified, enable the authorities to gauge the acceptability of a given project and provide those responsible for waste management with a basis for making decisions. In short, these principles constitute the framework of a suitably safety-oriented waste management policy. The more general criteria correspond to the protection objectives established by the national authorities on the basis of principles and recommendations formulated by international organizations, in particular the ICRP and the IAEA. They apply to any underground disposal system considered as a whole. The more specific criteria provide a means of evaluating the degree to which the various components of the disposal system meet the general criteria. They must also take account of the interaction between these components. As the ultimate aim is the overall safety of the disposal system, individual components can be adjusted to compensate for the performance of others with respect to the criteria. This is the approach adopted by the international bodies and national authorities in developing acceptability criteria for the final underground radioactive disposal systems to be used during the operational and post-operational phases respectively. The main criteria are reviewed and an attempt is made to assess the importance of the specific criteria according to the different types of disposal systems. (author)

Hydrogen production from municipal solid waste

Energy Technology Data Exchange (ETDEWEB)

Wallman, P.H.; Richardson, J.H.; Thorsness, C.B. [and others

1996-06-28

We have modified a Municipal Solid Waste (MSW) hydrothermal pretreatment pilot plant for batch operation and blowdown of the treated batch to low pressure. We have also assembled a slurry shearing pilot plant for particle size reduction. Waste paper and a mixture of waste paper/polyethylene plastic have been run in the pilot plant with a treatment temperature of 275{degrees}C. The pilot-plant products have been used for laboratory studies at LLNL. The hydrothermal/shearing pilot plants have produced acceptable slurries for gasification tests from a waste paper feedstock. Work is currently underway with combined paper/plastic feedstocks. When the assembly of the Research Gasification Unit at Texaco (feed capacity approximately 3/4-ton/day) is complete (4th quarter of FY96), gasification test runs will commence. Laboratory work on slurry samples during FY96 has provided correlations between slurry viscosity and hydrothermal treatment temperature, degree of shearing, and the presence of surfactants and admixed plastics. To date, pumpable slurries obtained from an MSW surrogate mixture of treated paper and plastic have shown heating values in the range 13-15 MJ/kg. Our process modeling has quantified the relationship between slurry heating value and hydrogen yield. LLNL has also performed a preliminary cost analysis of the process with the slurry heating value and the MSW tipping fee as parameters. This analysis has shown that the overall process with a 15 MJ/kg slurry gasifier feed can compete with coal-derived hydrogen with the assumption that the tipping fee is of the order $50/ton.

Wastes and by-products - alternatives for agricultural use

International Nuclear Information System (INIS)

Boles, J.L.; Craft, D.J.; Parker, B.R.

1994-01-01

Top address a growing national problem with generation of wastes and by-products, TVA has been involved for several years with developing and commercializing environmentally responsible practices for eliminating, minimizing, or utilizing various wastes/by-products. In many cases, reducing waste generation is impractical, but the wastes/by-products can be converted into other environmentally sound products. In some instances, conversion of safe, value-added agricultural products in the best or only practical alternative. TVA is currently involved with a diversity of projects converting wastes/by-products into safe, economical, and agriculturally beneficial products. Environmental improvement projects have involved poultry litter, cellulosic wastes, used battery acid, ammonium sulfate fines, lead smelting effluents, deep-welled sulfuric acid/ammonium bisulfate solutions, wood ash, waste magnesium ammonium sulfate slurry from recording tape production, and ammunition plant waste sodium nitrate/ammonium nitrate streams

Wastes

International Nuclear Information System (INIS)

Bovard, Pierre

The origin of the wastes (power stations, reprocessing, fission products) is determined and the control ensuring the innocuity with respect to man, public acceptance, availability, economics and cost are examined [fr

A proposed risk acceptance criterion for nuclear fuel waste disposal

International Nuclear Information System (INIS)

Mehta, K.

1985-06-01

The need to establish a radiological protection criterion that applies specifically to disposal of high level nuclear fuel wastes arises from the difficulty of applying the present ICRP recommendations. These recommendations apply to situations in which radiological detriment can be actively controlled, while a permanent waste disposal facility is meant to operate without the need for corrective actions. Also, the risks associated with waste disposal depend on events and processes that have various probabilities of occurrence. In these circumstances, it is not suitable to apply standards that are based on a single dose limit as in the present ICRP recommendations, because it will generally be possible to envisage events, perhaps rare, that would lead to doses above any selected limit. To overcome these difficulties, it is proposed to base a criterion for acceptability on a set of dose values and corresponding limiting values of probabilities; this set of values constitutes a risk-limit line. A risk-limit line suitable for waste disposal is proposed that has characteristics consistent with the basic philosophy of the ICRP and UNSCEAR recommendations, and is based on levels on natural background radiation

Energy and wastes. Chapter 1

International Nuclear Information System (INIS)

2002-01-01

In the Chapter 1 'Energy and wastes' it is shown the wastes generation inevitability at power production, because there are no absolutely wasteless technologies. After energy production technologies analysis the data that nuclear energy is most ecologically acceptable at maintenance related radiation safety measures

An investigation into waste charges in Ireland, with emphasis on public acceptability.

Science.gov (United States)

Dunne, Louise; Convery, Frank J; Gallagher, Louise

2008-12-01

There are 34 local authorities in Ireland with legal responsibility to deal with waste arising in their jurisdictions. In 2003 the National government introduced legislation that allows local authorities to recover the costs of waste collection and disposal, and to do so by 'executive function', i.e., not requiring support or agreement by the relevant local political representatives. The year 2005 was set as the date by which implementation of a pay by weight or volume was to be introduced. The local authorities were given autonomy as to how they addressed this challenge, so we have - in theory - 34 potentially different experiences from which to learn. This paper examines the pay-as-you-throw (PAYT) waste system in Ireland as it develops in line with EU and National demands, with a view to assessing economic and environmental efficiency. All local authorities were surveyed and thirteen responded. While this only represents about 38% of the total number, it includes jurisdictions that contribute in total more than 50% of waste arising. Key figures in the policy and business community were also interviewed in order to identify how the charging schemes were implemented, and to what effect. These insights and parallel investigations are used to review the potential for problems regarding public acceptability of environmental taxes and examine the evidence for economic and environmental efficiency, as well as problem areas, using data from each of the responding local authority jurisdictions. Concentrating on the incentives and drivers across households, municipalities and private waste contractors, the variations in charging system, annual charges and landfill charges are compared where information was available. The various jurisdictions are also examined in terms of relative successes and problems encountered in the transition from fixed charge or free waste collection to PAYT systems. The Irish situation is placed in the context of the international literature on

Characterization of waste from nanoenabled products

DEFF Research Database (Denmark)

Heggelund, Laura Roverskov

or particle number in the products. Overall, the most common product applications for ENMs are the “Health & Fitness” or “Home & Garden” sector, which was still the case, despite the increasing number of nanoproducts. The product inventories PEN CPI and The Nanodatabase are based on manufacturers’ claims...... and in a range of product applications (e.g. in cosmetics, textiles and food containers). By utilising The Nanodatabase product inventory, a method was developed for analysing the distribution of ENMs in waste, which involved the estimation of ENM fate in selected waste treatments based on their main matrix...... of nanoproducts available, the potential release of ENMs from these products would have to be understood to perform a risk assessment of these products. Since ENMs are considered possible contaminants of the solid waste, it is important to include nano-specific characterisation tests in waste characterisation...

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

Science.gov (United States)

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

2013-11-01

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

Waste Acceptance Testing of Secondary Waste Forms: Cast Stone, Ceramicrete and DuraLith

International Nuclear Information System (INIS)

Mattigod, Shas V.; Westsik, Joseph H.; Chung, Chul-Woo; Lindberg, Michael J.; Parker, Kent E.

2011-01-01

To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions has initiated secondary-waste-form testing work at Pacific Northwest National Laboratory (PNNL). In anticipation of a down-selection process for a waste form for the Solidification Treatment Unit to be added to the ETF, PNNL is conducting tests on four candidate waste forms to evaluate their ability to meet potential waste acceptance criteria for immobilized secondary wastes that would be placed in the IDF. All three waste forms demonstrated compressive strengths above the minimum 3.45 MPa (500 psi) set as a target for cement-based waste forms. Further, none of the waste forms showed any significant degradation in compressive strength after undergoing thermal cycling (30 cycles in a 10 day period) between -40 C and 60 C or water immersion for 90 days. The three leach test methods are intended to measure the diffusion rates of contaminants from the waste forms. Results are reported in terms of diffusion coefficients and a leachability index (LI) calculated based on the diffusion coefficients. A smaller diffusion coefficient and a larger LI are desired. The NRC, in its Waste Form Technical Position (NRC 1991), provides recommendations and guidance regarding methods to demonstrate waste stability for land disposal of radioactive waste. Included is a recommendation to conduct leach tests using the ANS 16.1 method. The resulting leachability index (LI) should be greater than 6.0. For Hanford secondary wastes, the LI > 6.0 criterion applies to sodium leached from the waste form. For technetium and iodine, higher targets of LI > 9 for Tc and LI > 11 for iodine have been set based on early waste-disposal risk and performance assessment analyses. The results of these three leach tests conducted for a total time between 11days (ASTM C1308) to 90 days (ANS 16.1) showed: (1) Technetium diffusivity: ANSI/ANS 16.1, ASTM C1308, and EPA 1315 tests indicated that

Waste Acceptance Testing of Secondary Waste Forms: Cast Stone, Ceramicrete and DuraLith

Energy Technology Data Exchange (ETDEWEB)

Mattigod, Shas V.; Westsik, Joseph H.; Chung, Chul-Woo; Lindberg, Michael J.; Parker, Kent E.

2011-08-12

To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions has initiated secondary-waste-form testing work at Pacific Northwest National Laboratory (PNNL). In anticipation of a down-selection process for a waste form for the Solidification Treatment Unit to be added to the ETF, PNNL is conducting tests on four candidate waste forms to evaluate their ability to meet potential waste acceptance criteria for immobilized secondary wastes that would be placed in the IDF. All three waste forms demonstrated compressive strengths above the minimum 3.45 MPa (500 psi) set as a target for cement-based waste forms. Further, none of the waste forms showed any significant degradation in compressive strength after undergoing thermal cycling (30 cycles in a 10 day period) between -40 C and 60 C or water immersion for 90 days. The three leach test methods are intended to measure the diffusion rates of contaminants from the waste forms. Results are reported in terms of diffusion coefficients and a leachability index (LI) calculated based on the diffusion coefficients. A smaller diffusion coefficient and a larger LI are desired. The NRC, in its Waste Form Technical Position (NRC 1991), provides recommendations and guidance regarding methods to demonstrate waste stability for land disposal of radioactive waste. Included is a recommendation to conduct leach tests using the ANS 16.1 method. The resulting leachability index (LI) should be greater than 6.0. For Hanford secondary wastes, the LI > 6.0 criterion applies to sodium leached from the waste form. For technetium and iodine, higher targets of LI > 9 for Tc and LI > 11 for iodine have been set based on early waste-disposal risk and performance assessment analyses. The results of these three leach tests conducted for a total time between 11days (ASTM C1308) to 90 days (ANS 16.1) showed: (1) Technetium diffusivity: ANSI/ANS 16.1, ASTM C1308, and EPA 1315 tests indicated that

Defining waste acceptance criteria for the Hanford Replacement Cross-Site Transfer System

International Nuclear Information System (INIS)

Hudson, J.D.

1996-04-01

This document provides a methodology for defining waste acceptance criteria for the Hanford Replacement Cross-Site Transfer System (RCSTS). This methodology includes characterization, transport analysis, and control. A framework is described for each of these functions. A tool was developed for performing the calculations associated with the transport analysis. This tool, a worksheet that is available in formats acceptable for a variety of PC spreadsheet programs, enables a comparison of the pressure required to transport a given slurry at a rate that particulate suspension is maintained to the pressure drop available from the RCSTS

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

WRAP low level waste (LLW) glovebox acceptance test report

International Nuclear Information System (INIS)

Leist, K.J.

1998-01-01

In June 28, 1997, the Low Level Waste (LLW) glovebox was tested using glovebox acceptance test procedure 13031A-85. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, lidder/delidder device and the supercompactor were also conducted. As of November 24, 1997, 2 of the 131 test exceptions that affect the LLW glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test Exceptions are provided as appendices to this report

WRAP low level waste (LLW) glovebox acceptance test report

Energy Technology Data Exchange (ETDEWEB)

Leist, K.J.

1998-02-17

In June 28, 1997, the Low Level Waste (LLW) glovebox was tested using glovebox acceptance test procedure 13031A-85. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, lidder/delidder device and the supercompactor were also conducted. As of November 24, 1997, 2 of the 131 test exceptions that affect the LLW glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test Exceptions are provided as appendices to this report.

Development of performance assessment methodology for establishment of quantitative acceptance criteria of near-surface radioactive waste disposal

Energy Technology Data Exchange (ETDEWEB)

Kim, C. R.; Lee, E. Y.; Park, J. W.; Chang, G. M.; Park, H. Y.; Yeom, Y. S. [Korea Hydro and Nuclear Power Co., Ltd., Seoul (Korea, Republic of)

2002-03-15

The contents and the scope of this study are as follows : review of state-of-the-art on the establishment of waste acceptance criteria in foreign near-surface radioactive waste disposal facilities, investigation of radiological assessment methodologies and scenarios, investigation of existing models and computer codes used in performance/safety assessment, development of a performance assessment methodology(draft) to derive quantitatively radionuclide acceptance criteria of domestic near-surface disposal facility, preliminary performance/safety assessment in accordance with the developed methodology.

241-AZ-101 Waste Tank Color Video Camera System Shop Acceptance Test Report

Energy Technology Data Exchange (ETDEWEB)

WERRY, S.M.

2000-03-23

This report includes shop acceptance test results. The test was performed prior to installation at tank AZ-101. Both the camera system and camera purge system were originally sought and procured as a part of initial waste retrieval project W-151.

241-AZ-101 Waste Tank Color Video Camera System Shop Acceptance Test Report

International Nuclear Information System (INIS)

WERRY, S.M.

2000-01-01

This report includes shop acceptance test results. The test was performed prior to installation at tank AZ-101. Both the camera system and camera purge system were originally sought and procured as a part of initial waste retrieval project W-151

Nuclear waste and public acceptance. A study about the situation in the Netherlands

International Nuclear Information System (INIS)

Damveld, H.

1999-01-01

The author bases the paper and study on the concept of the risk society coined by the sociologist Ulrich Beck. Very briefly, risk society means that in modern societies the basic conflicts have shifted from the distribution of prosperity to distribution of risks. The author points out five important factors affecting the willingness to accept a risk, which all have negative indication for the case of nuclear energy. 1. Catastrophe effect: The willingness to accept a more probable risk with less serious consequences is greater than the willingness to accept an extremely unlikely risk with serious consequences. Nuclear energy is considered to be a risk with catastrophe effect. 2. Justice factor: This factor too plays a central role in the negative assessment of nuclear energy. It is considered to be unjust to impose risks on future generations. 3. Voluntariness: The acceptance of a risk increases with the voluntariness. But nuclear energy is not considered to be a voluntary risk. 4. Confidence: The extent of confidence is an important factor determing how information on a possible risk will be assessed. In the Netherlands 68 percent of the population does not trust that the government will provide immediate and honest information on nuclear accidents. 5. Avoidability: An inevitable risk is more likely to be accepted than an avoidable risk. If already produced waste is involved and if there is even a chance that the nuclear power station concerned will be shut-down, the population is more likely to accept the final repository than if it were a case of searching for a final repository for waste not yet produced. (orig.) [de

Production of Fungal Glucoamylase for Glucose Production from Food Waste

Directory of Open Access Journals (Sweden)

Carol Sze Ki Lin

2013-09-01

Full Text Available The feasibility of using pastry waste as resource for glucoamylase (GA production via solid state fermentation (SSF was studied. The crude GA extract obtained was used for glucose production from mixed food waste. Our results showed that pastry waste could be used as a sole substrate for GA production. A maximal GA activity of 76.1 ± 6.1 U/mL was obtained at Day 10. The optimal pH and reaction temperature for the crude GA extract for hydrolysis were pH 5.5 and 55 °C, respectively. Under this condition, the half-life of the GA extract was 315.0 minutes with a deactivation constant (kd 2.20 × 10−3minutes−1. The application of the crude GA extract for mixed food waste hydrolysis and glucose production was successfully demonstrated. Approximately 53 g glucose was recovered from 100 g of mixed food waste in 1 h under the optimal digestion conditions, highlighting the potential of this approach as an alternative strategy for waste management and sustainable production of glucose applicable as carbon source in many biotechnological processes.

Production of Fungal Glucoamylase for Glucose Production from Food Waste

Science.gov (United States)

Lam, Wan Chi; Pleissner, Daniel; Lin, Carol Sze Ki

2013-01-01

The feasibility of using pastry waste as resource for glucoamylase (GA) production via solid state fermentation (SSF) was studied. The crude GA extract obtained was used for glucose production from mixed food waste. Our results showed that pastry waste could be used as a sole substrate for GA production. A maximal GA activity of 76.1 ± 6.1 U/mL was obtained at Day 10. The optimal pH and reaction temperature for the crude GA extract for hydrolysis were pH 5.5 and 55 °C, respectively. Under this condition, the half-life of the GA extract was 315.0 minutes with a deactivation constant (kd) 2.20 × 10−3 minutes−1. The application of the crude GA extract for mixed food waste hydrolysis and glucose production was successfully demonstrated. Approximately 53 g glucose was recovered from 100 g of mixed food waste in 1 h under the optimal digestion conditions, highlighting the potential of this approach as an alternative strategy for waste management and sustainable production of glucose applicable as carbon source in many biotechnological processes. PMID:24970186

Evaluation of ISDP Batch 2 Qualification Compliance to 512-S, DWPF, Tank Farm, and Saltstone Waste Acceptance Criteria

Energy Technology Data Exchange (ETDEWEB)

Shafer, A.

2010-05-05

The purpose of this report is to document the acceptability of the second macrobatch (Salt Batch 2) of Tank 49H waste to H Tank Farm, DWPF, and Saltstone for operation of the Interim Salt Disposition Project (ISDP). Tank 49 feed meets the Waste Acceptance Criteria (WAC) requirements specified by References 11, 12, and 13. Salt Batch 2 material is qualified and ready to be processed through ARP/MCU to the final disposal facilities.

Determination of acceptable risk criteria for nuclear waste management

International Nuclear Information System (INIS)

Cohen, J.J.

1977-01-01

The initial phase of the work performed during FY 1977 consisted of performing a ''scoping'' study to define issues, determine an optimal methodology for their resolution, and compile a data base for acceptable risk criteria development. The issues, spanning technical, psychological, and ethical dimensions, were categorized in seven major areas: (1) unplanned or accidental events, (2) present vs future risks, (3) institutional controls and retrievability, (4) dose-response mechanism and uncertainty, (5) spatial distribution of exposed populations, (6) different types of nuclear wastes, and (7) public perception. The optimum methodology for developing ARC was determined to be multi-attribute decision analysis encompassing numerous specific techniques for choosing, from among several alternatives, the optimal course of action when the alternatives are constrained to meet specified attributes. The data base developed during the study comprises existing regulations and guidelines, maximum permissible dose, natural geologic hazards, nonradioactive hazardous waste practices, bioethical perspectives, and data from an opinion survey

Determination of acceptable risk criteria for nuclear waste management

Energy Technology Data Exchange (ETDEWEB)

Cohen, J.J.

1977-10-21

The initial phase of the work performed during FY 1977 consisted of performing a ''scoping'' study to define issues, determine an optimal methodology for their resolution, and compile a data base for acceptable risk criteria development. The issues, spanning technical, psychological, and ethical dimensions, were categorized in seven major areas: (1) unplanned or accidental events, (2) present vs future risks, (3) institutional controls and retrievability, (4) dose-response mechanism and uncertainty, (5) spatial distribution of exposed populations, (6) different types of nuclear wastes, and (7) public perception. The optimum methodology for developing ARC was determined to be multi-attribute decision analysis encompassing numerous specific techniques for choosing, from among several alternatives, the optimal course of action when the alternatives are constrained to meet specified attributes. The data base developed during the study comprises existing regulations and guidelines, maximum permissible dose, natural geologic hazards, nonradioactive hazardous waste practices, bioethical perspectives, and data from an opinion survey.

An Investigation of Biodiesel Production from Wastes of Seafood Restaurants

Directory of Open Access Journals (Sweden)

Nour Sh. El-Gendy

2014-01-01

Full Text Available This work illustrates a comparative study on the applicability of the basic heterogeneous calcium oxide catalyst prepared from waste mollusks and crabs shells (MS and CS, resp. in the transesterification of waste cooking oil collected from seafood restaurants with methanol for production of biodiesel. Response surface methodology RSM based on D-optimal deign of experiments was employed to study the significance and interactive effect of methanol to oil M : O molar ratio, catalyst concentration, reaction time, and mixing rate on biodiesel yield. Second-order quadratic model equations were obtained describing the interrelationships between dependent and independent variables to maximize the response variable (biodiesel yield and the validity of the predicted models were confirmed. The activity of the produced green catalysts was better than that of chemical CaO and immobilized enzyme Novozym 435. Fuel properties of the produced biodiesel were measured and compared with those of Egyptian petro-diesel and international biodiesel standards. The biodiesel produced using MS-CaO recorded higher quality than that produced using CS-CaO. The overall biodiesel characteristics were acceptable, encouraging application of CaO prepared from waste MS and CS for production of biodiesel as an efficient, environmentally friendly, sustainable, and low cost heterogeneous catalyst.

Nuclear waste in public acceptance

International Nuclear Information System (INIS)

Vastchenko, Svetlana V.

2003-01-01

The existing problem on a faithful acceptance of nuclear information by population is connected, to a considerable extent, with a bad nuclear 'reputation' because of a great amount of misrepresented and false information from 'the greens'. In contrast to a bare style of professionals often neglecting an emotional perception, a loud voice of 'the greens' appeals both to the head, and to the heart of the audience. People pattern their behaviour weakly on problems of safe application of different irradiation sources in industry, conditions of life, medicine and everyday life. Radiation danger of some sources is often exaggerated (computers, nuclear technologies, radiation treatment) and the danger of the others is, on the contrary, underestimated (nuclear and roentgen methods of diagnostics and medical treatment). The majority of our citizens do not know which level of radiation is normal and safe, which ways radioactive substances intake into the organism of a human being and how to diminish the dose load on the organism by simple measures. Only specialists can be orientated themselves in a great number of radiation units. Low level of knowledge of the population and false conceptions are connected with the fact that they are mainly informed about nuclear technologies from mass media, where the voice of 'Greenpeace' is loudly sounded, but they often give misrepresented and false information doing it in the very emotional form. In contrast to them, scientists-professionals often ignore a sensitive part of apprehending of information and do not attach importance to it. As a rule, the style of specialists is of a serious academician character when they meet with the public. People preconception to nuclear waste and distrust to a positive information concerning nuclear technologies are explained, to a considerable extent, by a bivalent type of thinking when people operate by two opposite conceptions only, such as 'there is' or 'there is not' (there is or there is not

Nuclear waste in public acceptance

Energy Technology Data Exchange (ETDEWEB)

Vastchenko, Svetlana V. [Joint Institute for Power and Nuclear Research - Sosny / National Academy of Science, A.K.Krasin Str., 99, Minsk 220109 (Belarus)

2003-07-01

The existing problem on a faithful acceptance of nuclear information by population is connected, to a considerable extent, with a bad nuclear 'reputation' because of a great amount of misrepresented and false information from 'the greens'. In contrast to a bare style of professionals often neglecting an emotional perception, a loud voice of 'the greens' appeals both to the head, and to the heart of the audience. People pattern their behaviour weakly on problems of safe application of different irradiation sources in industry, conditions of life, medicine and everyday life. Radiation danger of some sources is often exaggerated (computers, nuclear technologies, radiation treatment) and the danger of the others is, on the contrary, underestimated (nuclear and roentgen methods of diagnostics and medical treatment). The majority of our citizens do not know which level of radiation is normal and safe, which ways radioactive substances intake into the organism of a human being and how to diminish the dose load on the organism by simple measures. Only specialists can be orientated themselves in a great number of radiation units. Low level of knowledge of the population and false conceptions are connected with the fact that they are mainly informed about nuclear technologies from mass media, where the voice of 'Greenpeace' is loudly sounded, but they often give misrepresented and false information doing it in the very emotional form. In contrast to them, scientists-professionals often ignore a sensitive part of apprehending of information and do not attach importance to it. As a rule, the style of specialists is of a serious academician character when they meet with the public. People preconception to nuclear waste and distrust to a positive information concerning nuclear technologies are explained, to a considerable extent, by a bivalent type of thinking when people operate by two opposite conceptions only, such as 'there is

Carrot Loss during Primary Production : Field Waste and Pack House Waste.

OpenAIRE

Bond, Rebekka

2016-01-01

Background: it has been suggested that roughly one-third of all food produced for human consumption is lost or wasted globally. The reduction of loss and waste is seen as an important societal issue with considerable ethical, ecological and economic implications. Fruit and vegetables have the highest wastage rates of any food products; (45 %). And a big part of this waste occurs during production, but empirical data on loss during primary production is limited. Carrots are an important hortic...

Processing of basalt fiber production waste

Science.gov (United States)

Sevostyanov, V. S.; Shatalov, A. V.; Shatalov, V. A.; Golubeva, U. V.

2018-03-01

The production of mineral rock wool forms a large proportion of off-test waste products. In addition to the cost of their production, there are costs for processing and utilization, such as transportation, disposal and preservation. Besides, wastes have harmful effect on the environment. This necessitates research aimed to study the stress-related characteristics of materials, their recyclability and use in the production of heat-saving products.

Formulation of criteria for pollution control on cement products produced from solid wastes in China.

Science.gov (United States)

Yang, Yufei; Huang, Qifei; Yang, Yu; Huang, Zechun; Wang, Qi

2011-08-01

The process of producing cement products from solid waste can increase the level of pollutants in the cement products. Therefore, it is very important to establish a pollution control standard for cement products to protect the environment and human health. This paper presents acceptance limits for the availability of heavy metals in cement products which have been produced from solid wastes and explains how the limits have been calculated. The approach and method used to formulate these criteria were based on EN 12920. The typical exposure scenarios used in this paper involve concrete being used for drinking water supply pipelines and concrete pavements and are based on an analysis of typical applications of cement in China, and the potential for contact with water. The parameters of a tank test which was based on NEN 7375 were set in accordance with the environmental conditions of typical scenarios in China. Mechanisms controlling the release of heavy metals in concrete and a model for that release were obtained using the leaching test. Finally, based on acceptance criteria for drinking water and groundwater quality in China, limit values for the availability of heavy metals in concrete were calculated. Copyright © 2011 Elsevier Ltd. All rights reserved.

Uses for waste diary products

Energy Technology Data Exchange (ETDEWEB)

Burgiss, K J

1980-06-01

Processing methods of waste dairy products are described. The major waste dairy product is whey, which is said to account for 20% of the total volume of milk processed. Individual methods of whey processing include the manufacture of lactose, whey demineralization in the preparation of babyfood, whey protein recovery by ultrafiltration and alcohol production. Two new techniques, lactose hydrolysis to increase the sweetness of lactose and reverse osmosis for concentration are also mentioned.

Immobilisation of MTR waste in cement (product evaluation). Final report. December 1987

International Nuclear Information System (INIS)

Howard, C.G.; Lee, D.J.

1988-01-01

The enriched uranium/aluminium fuel used in Material Testing Reactors is reprocessed at Dounreay Nuclear Power Development Establishment (DNE). The main chemical component of the liquid waste produced by this process is acid deficient aluminium nitrate. This is stored in stainless steel tanks at DNE. As a result of work carried out under the UKAEA radioactive waste management programme a decision was taken to immobilise the waste in cement. The programme had two main components, plant design and development of the cementation process. The plant for the cementation of MTR waste is under construction and will be commissioned in 1988/9. The primary objective of this project is to find a suitable process for changing the highly mobile radioactive waste into an inert stable solid. Work carried out on the development of the immobilisation process showed that a conditioning stage (neutralisation) is required to make the acid waste compatible with cement. Small scale experiments showed that adding Ordinary Portland Cement blended with ground granulated Blast Furnace Slag to Simulant MTR Liquor produces an acceptable product. The process has been demonstrated at full scale (200 litres) and the products have been subjected to an extensive programme of destructive and non-destructive testing. Specimens have been tested up to 1200 days after manufacture and show no significant signs of deterioration even when stored underwater or when subjected to freeze thaw cycling. Development work has also shown that the process can successfully immobilise simulant MTR liquor over a wide range of liquor concentrations. The programme therefore successfully produced a formulation that met all the requirements of both the process and product specification. (author)

Radioactivity distribution in phosphate products, by-products, effluents, and wastes

International Nuclear Information System (INIS)

Guimond, R.J.; Windham, S.T.

1975-08-01

Phosphate rock throughout the world contains uranium in concentrations ranging from a few ppM to a few hundred ppM. In the United States, phosphate rock normally contains between 100 to 150 ppM uranium. Mining and processing of these ores redistributes much of the uranium daughters among the various products, by-products, and wastes. These materials are then widely dispersed throughout the environment. This redistribution may lead to increased exposure of the public to these naturally-occurring radionuclides. In determining the magnitude of the population exposure caused by this redistribution and in developing environmental standards and controls to prevent contamination of the biosphere from these naturally-occurring radionuclides it is necessary to determine the concentrations and total quantities of these radionuclides in the products, by-products, effluents and wastes of phosphate mining and manufacturing. Samples of phosphate ores, products, by-products, effluents, and wastes were obtained and analyzed for their radioactivity content. Quantities of radioactivity entering the environment through various products, by-products, effluents, and wastes were estimated

Production of Biogas from wastes Blended with CowDung for Electricity generation-A Case study

Science.gov (United States)

Muthu, D.; Venkatasubramanian, C.; Ramakrishnan, K.; Sasidhar, Jaladanki

2017-07-01

The country’s production of solid waste generation is piling up year after year and the generation of Bio-Gas finds a fruitful solution to overcome this problem. This technology can contribute to energy conservation if the economic viability and social acceptance of this technology are favorable. Our campus has a number of hostel buildings which generates large quantum of kitchen waste and sewage per day. This research will have process ofcarrying out survey, characterization of kitchen waste from several kitchens & Canteens and knowing the potential for biogas production. The waste generated from kitchen and sewage from the hostels is given as feedstock to produce 600 m3 of biogas per day with cow dung as byproduct. The methane gas generated from Biogas is purified and this is used for power generation. Two biogas engine generators of 30 kVA and 50 kVA were installed. This power is used for backup power for girl’s hostel lighting load. From this study it is concluded that the generation of Biogas production and its usage for power production is the best option to handle these large quantum of sewage, kitchen waste generated from various buildings and also treated effluent from biogas plant and the biomass generated is a wealth for doing agriculture for any community ultimately it protects the environment.

40 CFR 268.20 - Waste specific prohibitions-Dyes and/or pigments production wastes.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Waste specific prohibitions-Dyes and/or pigments production wastes. 268.20 Section 268.20 Protection of Environment ENVIRONMENTAL... Disposal § 268.20 Waste specific prohibitions—Dyes and/or pigments production wastes. (a) Effective August...

Bio-hydrogen production from renewable organic wastes

Energy Technology Data Exchange (ETDEWEB)

Shihwu Sung

2004-04-30

Methane fermentation has been in practice over a century for the stabilization of high strength organic waste/wastewater. Although methanogenesis is a well established process and methane--the end-product of methanogenesis is a useful energy source; it is a low value end product with relatively less energy content (about 56 kJ energy/g CH{sub 4}). Besides, methane and its combustion by-product are powerful greenhouse gases, and responsible for global climate change. So there is a pressing need to explore alternative environmental technologies that not only stabilize the waste/wastewater but also generate benign high value end products. From this perspective, anaerobic bioconversion of organic wastes to hydrogen gas is an attractive option that achieves both goals. From energy security stand point, generation of hydrogen energy from renewable organic waste/wastewater could substitute non-renewable fossil fuels, over two-third of which is imported from politically unstable countries. Thus, biological hydrogen production from renewable organic waste through dark fermentation represents a critically important area of bioenergy production. This study evaluated both process engineering and microbial physiology of biohydrogen production.

Examining extrinsic factors that influence product acceptance: a review.

Science.gov (United States)

Li, X E; Jervis, S M; Drake, M A

2015-05-01

Drivers of liking (DOL) studies are useful for product development to formulate acceptable products; however, DOL alone are insufficient for understanding why a product is purchased and repurchased, which is ultimately the indication of a successful product. Ultimately sensory attributes drive product success (that is, repeat and continued purchase). However, ignoring the importance of extrinsic factors may neglect the vital product attributes responsible for the initial purchase, which may in turn, affect repeat purchase. The perception of sensory attributes assessed by DOL is mitigated by external perceptions of quality. If the sensory attributes do not deliver based upon the quality cues, the product will not be acceptable. Four key extrinsic factors that affect DOL are the perceived satiety, brand and labeling, price, and the emotional impact to decision making. In order to more thoroughly understand what the DOL for a product is, these 4 product cues should be considered in conjunction with sensory attribute perception to gain a holistic understanding of product acceptance. © 2015 Institute of Food Technologists®

Product specific emissions from municipal solid waste landfills

DEFF Research Database (Denmark)

Nielsen, Per Henning; Hauschild, Michael Zwicky

1998-01-01

For the inventory analysis of environmental impacts associated with products in LCA there is a great need for estimates of emissions from waste products disposed at municipal solid waste landfills (product specific emissions). Since product specific emissions can not be calculated or measured...... directly at the landfills, they must be estimated by modelling of landfill processes. This paper presents a landfill model based on a large number of assumptions and approximations concerning landfill properties, waste product properties and characteristics of various kinds of environmental protection...... systems (e.g. landfill gas combustion units and leachate treatment units). The model is useful for estimation of emissions from waste products disposed in landfills and it has been made operational in the computer tool LCA-LAND presented in a following paper. In the model, waste products are subdivided...

Contested environmental policy infrastructure: Socio-political acceptance of renewable energy, water, and waste facilities

International Nuclear Information System (INIS)

Wolsink, Maarten

2010-01-01

The construction of new infrastructure is hotly contested. This paper presents a comparative study on three environmental policy domains in the Netherlands that all deal with legitimising building and locating infrastructure facilities. Such infrastructure is usually declared essential to environmental policy and claimed to serve sustainability goals. They are considered to serve (proclaimed) public interests, while the adverse impact or risk that mainly concerns environmental values as well is concentrated at a smaller scale, for example in local communities. The social acceptance of environmental policy infrastructure is institutionally determined. The institutional capacity for learning in infrastructure decision-making processes in the following three domains is compared: 1.The implementation of wind power as a renewable energy innovation; 2.The policy on space-water adaptation, with its claim to implement a new style of management replacing the current practice of focusing on control and 'hard' infrastructure; 3.Waste policy with a focus on sound waste management and disposal, claiming a preference for waste minimization (the 'waste management hierarchy'). All three cases show a large variety of social acceptance issues, where the appraisal of the impact of siting the facilities is confronted with the desirability of the policies. In dealing with environmental conflict, the environmental capacity of the Netherlands appears to be low. The policies are frequently hotly contested within the process of infrastructure decision-making. Decision-making on infrastructure is often framed as if consensus about the objectives of environmental policies exists. These claims are not justified, and therefore stimulating the emergence of environmental conflicts that discourage social acceptance of the policies. Authorities are frequently involved in planning infrastructure that conflicts with their officially proclaimed policy objectives. In these circumstances, they are

Preliminary criticality study supporting transuranic waste acceptance into the plasma hearth process

International Nuclear Information System (INIS)

Slate, L.J.; Santee, G.E. Jr.

1996-01-01

This study documents preliminary scoping calculations to address criticality issues associated with the processing of transuranic (TRU) waste and TRU mixed waste in the Plasma Hearth Process (PHP) Test Project. To assess the criticality potential associated with processing TRU waste, the process flow in the PHP is evaluated to identify the stages where criticality could occur. A criticality analysis methodology is then formulated to analyze the criticality potential. Based on these analyses, TRU acceptance criteria can be defined for the PHP. For the current level of analysis, the methodology only assesses the physical system as designed and does not address issues associated with the criticality double contingency principle. The analyses suggest that criticality within the PHP system and within the planned treatment residue (stag) containers does not pose a criticality hazard even when processing waste feed drums containing a quantity of TRU greater than would be reasonably expected. The analyses also indicate that the quantity of TRU that can be processed during each batch is controlled by moving and storage conditions for the resulting slag collection drums

Product control of radioactive waste

International Nuclear Information System (INIS)

Warnecke, E.; Giller, H.

1989-09-01

The aim of the seminar was to give a survey of product quality control and to find out whether the producers/conditioners of waste set and fulfil requirements for the quality of the waste. The program included the following main areas: Random sample tests; Container tests; Process qualification and inspection, and Inspections of waste from fuel element reprocessing abroad. In other lectures, there are reports on measures for producers of waste for guaranteeing the final storage requirements, on quality assurance measurements in the conditioning of waste from large research establishments and from fuel element manufacture. The calling up of waste containers and the documentation of waste data is also introduced. (orig./HP) [de

High-level waste processing and disposal

International Nuclear Information System (INIS)

Crandall, J.L.; Krause, H.; Sombret, C.; Uematsu, K.

1984-01-01

The national high-level waste disposal plans for France, the Federal Republic of Germany, Japan, and the United States are covered. Three conclusions are reached. The first conclusion is that an excellent technology already exists for high-level waste disposal. With appropriate packaging, spent fuel seems to be an acceptable waste form. Borosilicate glass reprocessing waste forms are well understood, in production in France, and scheduled for production in the next few years in a number of other countries. For final disposal, a number of candidate geological repository sites have been identified and several demonstration sites opened. The second conclusion is that adequate financing and a legal basis for waste disposal are in place in most countries. Costs of high-level waste disposal will probably add about 5 to 10% to the costs of nuclear electric power. The third conclusion is less optimistic. Political problems remain formidable in highly conservative regulations, in qualifying a final disposal site, and in securing acceptable transport routes

Waste valorization by biotechnological conversion into added value products.

Science.gov (United States)

Liguori, Rossana; Amore, Antonella; Faraco, Vincenza

2013-07-01

Fossil fuel reserves depletion, global warming, unrelenting population growth, and costly and problematic waste recycling call for renewable resources of energy and consumer products. As an alternative to the 100 % oil economy, production processes based on biomass can be developed. Huge amounts of lignocellulosic wastes are yearly produced all around the world. They include agricultural residues, food farming wastes, "green-grocer's wastes," tree pruning residues, and organic and paper fraction of urban solid wastes. The common ways currently adopted for disposal of these wastes present environmental and economic disadvantages. As an alternative, processes for adding value to wastes producing high added products should be developed, that is the upgrading concept: adding value to wastes by production of a product with desired reproducible properties, having economic and ecological advantages. A wide range of high added value products, such as enzymes, biofuels, organic acids, biopolymers, bioelectricity, and molecules for food and pharmaceutical industries, can be obtained by upgrading solid wastes. The most recent advancements of their production by biotechnological processes are overviewed in this manuscript.

Sampling and analysis strategies to support waste form qualification

International Nuclear Information System (INIS)

Westsik, J.H. Jr.; Pulsipher, B.A.; Eggett, D.L.; Kuhn, W.L.

1989-04-01

As part of the waste acceptance process, waste form producers will be required to (1) demonstrate that their glass waste form will meet minimum specifications, (2) show that the process can be controlled to consistently produce an acceptable waste form, and (3) provide documentation that the waste form produced meets specifications. Key to the success of these endeavors is adequate sampling and chemical and radiochemical analyses of the waste streams from the waste tanks through the process to the final glass product. This paper suggests sampling and analysis strategies for meeting specific statistical objectives of (1) detection of compositions outside specification limits, (2) prediction of final glass product composition, and (3) estimation of composition in process vessels for both reporting and guiding succeeding process steps. 2 refs., 1 fig., 3 tabs

Impact of community engagement on public acceptance towards waste-to-energy incineration projects: Empirical evidence from China.

Science.gov (United States)

Liu, Yong; Sun, Chenjunyan; Xia, Bo; Cui, Caiyun; Coffey, Vaughan

2018-02-20

As one of the most popular methods for the treatment of municipal solid waste (MSW), waste-to-energy (WTE) incineration offers effective solutions to deal with the MSW surge and globe energy issues. Nevertheless, the construction of WTE facilities faces considerable and strong opposition from local communities due to the perceived potential risks. The present study aims to understand whether, and how, community engagement improves local residents' public acceptance towards waste-to-energy (WTE) incineration facilities using a questionnaire survey conducted with nearby residents of two selected WTE incineration plants located in Zhejiang province, China. The results of data analysis using Structural Equation Modeling (SEM) reveal that firstly, a lower level of public acceptance exists among local residents of over the age of 35, of lower education levels, living within 3 km from the WTE Plant and from WTE incineration Plants which are under construction. Secondly, the public trust of local government and other authorities was positively associated with the public acceptance of the WTE incineration project, both directly and indirectly based on perceived risk. Thirdly, community engagement can effectively enhance public trust in local government and other authorities related to the WTE incineration project. The findings contribute to the literature on MSW treatment policy-making and potentially hazardous facility siting, by exploring the determinants of public acceptance towards WTE incineration projects. Copyright © 2018 Elsevier Ltd. All rights reserved.

Requirements on radioactive waste for disposal (waste acceptance requirements as of February 2017). Konrad repository; Anforderungen an endzulagernde radioaktive Abfaelle (Endlagerungsbedingungen, Stand: Februar 2017). Endlager Konrad

Energy Technology Data Exchange (ETDEWEB)

Kugel, Karin; Moeller, Kai (eds.)

2017-02-10

The Bundesamt fuer Strahlenschutz (BfS - Federal Office for Radiation Protection) has established waste acceptance requirements for the Konrad repository. These requirements were developed on the basis of the results of a site-specific safety assessment. They include general requirements on waste packages and specific requirements on waste forms and packagings as well as limitations for activities of individual radionuclides and limitations to masses of non-radioactive harmful substances. Requirements on documentation and delivery of waste packages were additionally included.

Assessment of LANL beryllium waste management documentation

International Nuclear Information System (INIS)

Danna, J.G.; Jennrich, E.A.; Lund, D.M.; Davis, K.D.; Hoevemeyer, S.S.

1991-04-01

The objective of this report is to determine present status of the preparation and implementation of the various high priority documents required to properly manage the beryllium waste generated at the Laboratory. The documents being assessed are: Waste Acceptance Criteria, Waste Characterization Plan, Waste Certification Plan, Waste Acceptance Procedures, Waste Characterization Procedures, Waste Certification Procedures, Waste Training Procedures and Waste Recordkeeping Procedures. Beryllium is regulated (as a dust) under 40 CFR 261.33 as ''Discarded commercial chemical products, off specification species, container residues and spill residues thereof.'' Beryllium is also identified in the 3rd thirds ruling of June 1, 1990 as being restricted from land disposal (as a dust). The beryllium waste generated at the Laboratory is handled separately because beryllium has been identified as a highly toxic carcinogenic material

Reduce, reuse, recycle: Acceptance of CO_2-utilization for plastic products

International Nuclear Information System (INIS)

Heek, Julia van; Arning, Katrin; Ziefle, Martina

2017-01-01

Global warming is a central threat for today's society caused by greenhouse gas emissions, mostly carbon dioxide emissions. Carbon dioxide capture and utilization (CCU) is a promising approach to reduce emissions and the use of expensive and limited fossil resources. Applying CCU, carbon dioxide (CO_2) can be incorporated as raw material during the manufacture of plastic products. While most of the studies address technical feasibilities, hardly any systematic research on public perception and acceptance of those specific products exists so far. This study empirically investigates the acceptance of CCU plastic products (mattress as example). First, interviews with experts and lay people revealed critical acceptance factors (CO_2 proportion, saving of fossil resources, disposal conditions, perceived health complaints). Their relative importance was detailed in two consecutive conjoint studies. Study 1 revealed disposal conditions and saving of fossil resources as essential for product selection, while the products’ CO_2 proportion was less important. In study 2, potential health complaints were integrated as well as individual levels of domain knowledge and risk perception, which significantly affected acceptance of CCU products. Recommendations concerning communication strategies for policy and industry were derived. - Highlights: • Study provides insights into the acceptance of specific CCU products. • Disposal conditions and savings of fossil resource are main drivers of acceptance. • Concerns about potential health effects act as major barrier especially for laypeople. • Perceived knowledge and risk perception affect CCU product acceptance. • Communication strategy recommendations for policy and industry are derived.

Participatory approach, acceptability and transparency of waste management LCAs: case studies of Torino and Cuneo.

Science.gov (United States)

Blengini, Gian Andrea; Fantoni, Moris; Busto, Mirko; Genon, Giuseppe; Zanetti, Maria Chiara

2012-09-01

The paper summarises the main results obtained from two extensive applications of Life Cycle Assessment (LCA) to the integrated municipal solid waste management systems of Torino and Cuneo Districts in northern Italy. Scenarios with substantial differences in terms of amount of waste, percentage of separate collection and options for the disposal of residual waste are used to discuss the credibility and acceptability of the LCA results, which are adversely affected by the large influence of methodological assumptions and the local socio-economic constraints. The use of site-specific data on full scale waste treatment facilities and the adoption of a participatory approach for the definition of the most sensible LCA assumptions are used to assist local public administrators and stakeholders showing them that LCA can be operational to waste management at local scale. Copyright © 2012 Elsevier Ltd. All rights reserved.

Energy from waste: a wholly acceptable waste-management solution

International Nuclear Information System (INIS)

Porteous, A.

1997-01-01

This paper briefly reviews the 'waste management hierarchy' and why it should be treated as a checklist and not a piece of unquestioning dogma. The role of energy from waste (EfW) is examined in depth to show that it is a rigorous and environmentally sound waste-management option which complements other components of the waste-management hierarchy and assists resource conservation. (Copyright (c) 1997 Elsevier Science B.V., Amsterdam. All rights reserved.)

Neighbourhood Acceptability of Poultry Farms Located in ...

African Journals Online (AJOL)

... due to poultry production in their neighbourhood. It was recommended that farmers should be encouraged to adopt technologies that can keep poultry litters dry and odourless. In addition, poultry farm locations should be sited far away from residential areas. Keywords: Poultry Farms, Acceptability, Waste management, ...

Alcohol production from pineapple waste

Energy Technology Data Exchange (ETDEWEB)

Ban-Koffi, L. (Ministry of Scientific Research, Abidjan (CI). Ivorian Center of Technological Research); Han, Y.W. (USDA, Southern Regional Research Center, New Orleans, LA (US))

1990-09-01

Saccharomyces cerevisiae and Zymomonas mobilis were grown on pineapple waste and their alcohol production characteristics compared. The pineapple waste consisted of 19% cellulose, 22% hemi-cellulose, 5% lignin and 53% cell soluble matters but concentration of soluble sugars, which included 5.2% sucrose, 3.1% glucose and 3.4% fructose, was relatively low and pretreatment of the substrate was needed. Pretreatment of pineapple waste with cellulase and hemi-cellulase and then fermentation with S. cerevisiae or Z. mobilis produced about 8% ethanol from pineapple waste in 48 h. (author).

Eco-efficient waste glass recycling: Integrated waste management and green product development through LCA

International Nuclear Information System (INIS)

Blengini, Gian Andrea; Busto, Mirko; Fantoni, Moris; Fino, Debora

2012-01-01

Highlights: ► A new eco-efficient recycling route for post-consumer waste glass was implemented. ► Integrated waste management and industrial production are crucial to green products. ► Most of the waste glass rejects are sent back to the glass industry. ► Recovered co-products give more environmental gains than does avoided landfill. ► Energy intensive recycling must be limited to waste that cannot be closed-loop recycled. - Abstract: As part of the EU Life + NOVEDI project, a new eco-efficient recycling route has been implemented to maximise resources and energy recovery from post-consumer waste glass, through integrated waste management and industrial production. Life cycle assessment (LCA) has been used to identify engineering solutions to sustainability during the development of green building products. The new process and the related LCA are framed within a meaningful case of industrial symbiosis, where multiple waste streams are utilised in a multi-output industrial process. The input is a mix of rejected waste glass from conventional container glass recycling and waste special glass such as monitor glass, bulbs and glass fibres. The green building product is a recycled foam glass (RFG) to be used in high efficiency thermally insulating and lightweight concrete. The environmental gains have been contrasted against induced impacts and improvements have been proposed. Recovered co-products, such as glass fragments/powders, plastics and metals, correspond to environmental gains that are higher than those related to landfill avoidance, whereas the latter is cancelled due to increased transportation distances. In accordance to an eco-efficiency principle, it has been highlighted that recourse to highly energy intensive recycling should be limited to waste that cannot be closed-loop recycled.

Feed Materials Production Center Waste Management Plan

International Nuclear Information System (INIS)

Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

1986-01-01

In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the waste generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF 2 , slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program

Production of metal waste forms from spent fuel treatment

International Nuclear Information System (INIS)

Westphal, B.R.; Keiser, D.D.; Rigg, R.H.; Laug, D.V.

1995-01-01

Treatment of spent nuclear fuel at Argonne National Laboratory consists of a pyroprocessing scheme in which the development of suitable waste forms is being advanced. Of the two waste forms being proposed, metal and mineral, the production of the metal waste form utilizes induction melting to stabilize the waste product. Alloying of metallic nuclear materials by induction melting has long been an Argonne strength and thus, the transition to metallic waste processing seems compatible. A test program is being initiated to coalesce the production of the metal waste forms with current induction melting capabilities

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

International Nuclear Information System (INIS)

Kortus, J.

1988-01-01

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

Perceived risks of nuclear fuel waste disposal: trust, compensation, and public acceptance in Canada

International Nuclear Information System (INIS)

Hine, D.W.; Summers, C.

1996-01-01

AECL's recommendation to place the high-level radioactive waste in corrosion resistant containers and bury it in underground vaults several hundred metres deep in the rock of the Canadian shield is presently under federal review. If and when the disposal concept is approved by the federal review panel, a search will begin for a suitable host community. Given that siting guidelines prevent the government from unilaterally imposing the waste on a reluctant community, identifying a suitable site may represent the single greatest obstacle to successfully implementing the disposal concept. Even if the concept is approved by the review panel, it may be very difficult to find a community that is willing to accept the waste. In the US, efforts to site an underground disposal facility for high-level nuclear waste at Yucca Mountain has run into strong opposition from local residents and politicians, resulting in long delays and major cost overruns

Framing ethical acceptability: a problem with nuclear waste in Canada.

Science.gov (United States)

Wilding, Ethan T

2012-06-01

Ethical frameworks are often used in professional fields as a means of providing explicit ethical guidance for individuals and institutions when confronted with ethically important decisions. The notion of an ethical framework has received little critical attention, however, and the concept subsequently lends itself easily to misuse and ambiguous application. This is the case with the 'ethical framework' offered by Canada's Nuclear Waste Management Organization (NWMO), the crown-corporation which owns and is responsible for the long-term management of Canada's high-level nuclear fuel waste. It makes a very specific claim, namely that it is managing Canada's long-lived radioactive nuclear fuel waste in an ethically responsible manner. According to this organization, what it means to behave in an ethically responsible manner is to act and develop policy in accordance with its ethical framework. What, then, is its ethical framework, and can it be satisfied? In this paper I will show that the NWMO's ethical and social framework is deeply flawed in two respects: (a) it fails to meet the minimum requirements of a code of ethic or ethical framework by offering only questions, and no principles or rules of conduct; and (b) if posed as principles or rules of conduct, some of its questions are unsatisfiable. In particular, I will show that one of its claims, namely that it seek informed consent from individuals exposed to risk of harm from nuclear waste, cannot be satisfied as formulated. The result is that the NWMO's ethical framework is not, at present, ethically acceptable.

Productivity studies of the nuclear waste programme

International Nuclear Information System (INIS)

Lundberg, Haakan

2002-08-01

The Swedish Nuclear Inspectorate reviews and supplements the SKB proposal for cost estimations for the nuclear waste programme. These estimations are of great importance for the determination of annual fees to the Nuclear Waste Fund and guarantee amounts in accordance with the Financing Act. The majority of the Nuclear Waste Fund's assets are invested in real interest bonds, issued by the Swedish state. The average duration for the Nuclear Waste Fund investments was 12.8 years at the end of December 2001. From July 1, 2002 on the Nuclear waste Fund investments will consist of nominal and real bonds on the official market. The Fund is increased in line with the Consumer Price Index (KPI). If real costs within the nuclear waste programme increase at a faster rate than the KPI, there is a risk that the Nuclear Waste Fund will be 'under balanced'. SKI has developed a weighted index, the KBS-3-index, to compare the SKB cost re-estimate with. Productivity changes have however no impact on these indices. The KBS-3-index indicates that there might be a risk that the de facto, cost increases will exceed KPI. An improved productivity might however balance the cost escalations. Productivity is normally defined as production divided by the input of production factors. The production can be a quantity measurement or the value added. A common approach is calculation of the labour productivity. The productivity development within different industries in Sweden and in EU varies, and is not only positive. The so called DEA method is used for productivity and efficiency measurements in public and private operations. Efficiency evaluations based on known norms are not made with the DEA models. Instead the evaluation is performed in relation to an empirically based reference technology, a relative efficiency. A selection or an optimisation of output is difficult for the nuclear waste programme. It is not possible to change parts of the nuclear waste programme to something else

Radioactive waste products - suitability for final disposal

International Nuclear Information System (INIS)

Merz, E.; Odoj, R.; Warnecke, E.

1985-06-01

48 papers were read at the conference. Separate records are available for all of them. The main problem in radioactive waste disposal was the long-term sealing to prevent pollution of the biosphere. Problems of conditioning, acceptance, and safety measures were discussed. Final disposal models and repositories were presented. (PW) [de

Towards zero waste production in the minerals and metals sector

Science.gov (United States)

Rankin, William J.

The production of mineral and metal commodities results in large quantities of wastes (solid, liquid and gaseous) at each stage of value-adding — from mining to manufacturing. Waste production (both consumer and non-consumer) is a major contributor to environmental degradation. Approaches to waste management in the minerals industry are largely `after the event'. These have moved progressively from foul-and-flee to dilute-and-disperse to end end-of-pipe treatments. There is now a need to move to approaches which aim to reduce or eliminate waste production at source. Modern waste management strategies include the application of cleaner production principles, the use of wastes as raw materials, the reengineering of process flowsheets to minimise waste production, and use of industrial symbioses through industrial ecology to convert wastes into useful by-products. This paper examines how these can be adopted by the minerals industry, with some recent examples. The financial, technical, systemic and regulatory drivers and barriers are also examined.

Cross-Site Transfer System at Hanford: long-term strategy for waste acceptance

International Nuclear Information System (INIS)

Shekarriz, A.; Onishi, Y.; Smith, P.A.; Sterner, M.; Rector, D.R.; Virden, J.

1997-02-01

This report summarizes results of a technical panel review of the current methodology for accepting waste for transport through the Hanford Replacement Cross-Site Transfer System (RCSTS), which was constructed to replace the existing pipelines that hydraulically connect the 200 West and 200 East areas. This report is a complement to an existing document (Hudson 1996); the methodology proposed in that document was refined based on panel recommendations. The refinements were focused around predicting and preventing the 3 main modes suspected of plugging the existing CSTS: precipitation, gelation, particle dropout/settling. The proposed analysis will require integration of computer modeling and laboratory experiments to build a defensible case for transportability of a proposed slurry composition for a given tank. This will be validated by recirculating actual tank waste, in-tank and in-farm, prior to transport. The panel's recommendation was that the probability of success of waste transfer would be greatly improved by integrating the predictive analysis with real-time control during RCSTS operation. The methodology will be optimized

Catalytic Transformation of Waste CO{sub 2} into Valuable Products

Energy Technology Data Exchange (ETDEWEB)

Anderson, Jason; Shepard, Peter; Valente, Ron

2013-09-30

Novomer’s novel materials contain up to 50% by mass CO{sub 2} and provide a unique platform for re-using CO{sub 2} from waste industrial sources and converting it into useful products. This Report covers the progress made by Novomer during the DOE funded project (DOE Award #: DE-FE0002474) under the “Carbon Capture and Sequestration from Industrial Sources and Innovative Concepts for Beneficial CO{sub 2} Use” program. This includes Phase 1 and Phase 2, including all three subphases of the latter. Novomer completed all technical and commercial objectives in both Phase 1 and Phase 2, including the six Phase 2 Objectives outlined in the SOPO within budget by the project end date of September 30, 2013. These are: validating the economics are competitive, validate the carbon footprint, validate acceptable product performance, verify robust manufacturing process, validate large markets exist, and qualify at least 3 products with customers.

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

Albert, R.

1992-01-01

The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and the Washington State Dangerous Waste Regulations, 173-303-040 (18). This waste is to be transferred to the Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington. This plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF (Section 4); and a list of the current and planned implementing procedures used in waste certification

Systems and methods of storing combustion waste products

Science.gov (United States)

Chen, Shen-En; Wang, Peng; Miao, Xiexing; Feng, Qiyan; Zhu, Qianlin

2016-04-12

In one aspect, methods of storing one or more combustion waste products are described herein. Combustion waste products stored by a method described herein can include solid combustion waste products such as coal ash and/or gaseous combustion products such as carbon dioxide. In some embodiments, a method of storing carbon dioxide comprises providing a carbon dioxide storage medium comprising porous concrete having a macroporous and microporous pore structure and flowing carbon dioxide captured from a combustion flue gas source into the pore structure of the porous concrete.

WASTE-FREE PRODUCTION TECHNOLOGY OF DRY MASHED POTATOES

Directory of Open Access Journals (Sweden)

G. V. Kalashnikov

2015-01-01

Full Text Available Summary. According to data on norms of consumption of vegetable production of scientific research institute of Food of the Russian Academy of Medical Science, potatoes win first place with norm of 120 kg a year on the person. In this regard much attention is paid to processing of potatoes that allows to prolong the term of its validity, and also to reduce the capacity of storages and to reduce transport transportations as 1 kg of a dry potatoes produсt is equivalent 7-8 kg of fresh potatoes. Thus industrial processing of potatoes on dry mashed potatoes allows to reduce losses of potatoes at storage and transportation, there is a possibility of enrichment of products vitamins and other useful components, its nutrition value remains better, conditions for complex processing of raw materials with full recycling and creations of stocks of products from potatoes on a crop failure case are created. Dry mashed potatoes are a product of long storage. On the basis of studying of the production technology of mashed potatoes the analysis of technological processes as sources of creation of waste, and the directions of recovery of secondary raw materials for complex waste-free technology of processing of potatoes are defined is provided. The waste-free technological scheme of processing of potatoes and production of dry instant mashed potatoes on the basis of dehydration and moisture thermal treatment a component providing recovery of secondary carbohydrate content raw materials in the form of waste of the main production is developed. The main stages of production of dry instant mashed potatoes are described. It is offered the technological scheme of a production line of mashed potatoes on the basis of waste-free technology. Advantages of the offered waste-free production technology of dry instant mashed potatoes with processing of secondary starch-containing raw materials are given.

CONSTRUCTION MATERIALS FROM WASTE PRODUCTS

Directory of Open Access Journals (Sweden)

Тахира Далиевна Сидикова

2016-02-01

Full Text Available We have studied the physical and chemical processes occurring during the thermal treatment of ceramic masses on the basis of compositions of natural raw materials and waste processing facilities. The study of structures of ceramic samples species has shown different types of crystalline phases.The results have shown that the waste of Kaytashsky tungsten-molybdenum ores (KVMR may be used as the main raw material to develop new compositions for ceramic materials. The optimal compositions of ceramic tiles for the masses and technological parameters of obtaining sintered materials based on the compositions of kaolin fireclay KVMR have been developed.It has been found that the use of the waste of Kaytashskoy tungsten-molybdenum ore (KVMR in the composition of the ceramic material will expand the raw material base of ceramic production, reduce the roasting temperature and the cost of ceramic materials and products.

Development of comprehensive waste acceptance criteria for commercial nuclear waste

International Nuclear Information System (INIS)

O'Hara, F.A.; Miller, N.E.; Ausmus, B.S.; Yates, K.R.; Means, J.L.; Christensen, R.N.; Kulacki, F.A.

1979-01-01

A detailed methodology is presented for the identification of the characteristics of commercial nuclear waste which may require criteria. This methodology is analyzed as a six-step process which begins with identification of waste operations and proceeds until the waste characteristics affecting the potential release of radionuclides are determined. All waste types and operations were analyzed using the methodology presented. Several illustrative example are included. It is found that thirty-three characteristics can be identified as possibly requiring criteria

Disposable products in the hospital waste stream.

OpenAIRE

Gilden, D. J.; Scissors, K. N.; Reuler, J. B.

1992-01-01

Use of disposable products in hospitals continues to increase despite limited landfill space and dwindling natural resources. We analyzed the use and disposal patterns of disposable hospital products to identify means of reducing noninfectious, nonhazardous hospital waste. In a 385-bed private teaching hospital, the 20 disposable products of which the greatest amounts (by weight) were purchased, were identified, and total hospital waste was tabulated. Samples of trash from three areas were so...

Prospective application of municipal solid wastes for energy production in Portugal

International Nuclear Information System (INIS)

Teixeira, Sandra; Monteiro, Eliseu; Silva, Valter; Rouboa, Abel

2014-01-01

Municipal solid waste (MSW) collection and disposal is a major urban environment issue in the world today. MSW management solutions have to be technologically feasible, legally and socially acceptable and environmentally and financially sustainable. European policy is pushing for a rational management of natural resources; a promising technological perspective today is waste valorisation, a process that involves sorting at the source, combined with material recycling and waste-to-energy conversion. In this paper, we analyze the evolution of the Portuguese MSW management system, criticize the environmental policy issues for MSW management in Portugal and identify weak points in the criteria used for the technologies selection. Portugal is facing multiple problems with MSW management and is attempting to tackle them by passing legislation in order to improve the performance of waste management systems. At the technological level, gasification increasingly presents as an efficient and viable alternative to incineration. Gasification is a waste-to-energy conversion scheme that offers an attractive solution to both waste disposal and energy problems. Waste gasification by plasma has been validated but the economic viability of this technology must be proven before to be accepted by the industry. - Highlights: • MSW collection and disposal are a major problem of urban environment. • Portugal is facing multiple problems and improving the MSW management system. • Gasification offers the most attractive solution to both waste disposal and energy problems. • Plasma gasification seems to be validated but the economic viability must be proven

77 FR 12293 - PCBs Bulk Product v. Remediation Waste

Science.gov (United States)

2012-02-29

.... Remediation Waste AGENCY: Environmental Protection Agency (EPA). ACTION: Request for Public Comment. SUMMARY... biphenyl (PCB) disposal regulations regarding PCB bulk product and PCB remediation waste. The proposed... regarding PCB bulk product and PCB remediation waste under regulations promulgated at 40 CFR part 761. The...

The DWPF waste form qualification program

International Nuclear Information System (INIS)

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

1994-01-01

Prior to the introduction of radioactive feed into the Defense Waste Processing Facility for immobilization in borosilicate glass an extensive waste qualification program must be completed. The DWPF must demonstrate its ability to comply with the Waste Acceptance Product Specifications. This ability is being demonstrated through laboratory and pilot scale work and will be completed after the full operation of the DWPF using various simulated feeds

Combustion of animal or vegetable based liquid waste products

International Nuclear Information System (INIS)

Wikman, Karin; Berg, Magnus

2002-04-01

In this project experiences from combustion of animal and vegetable based liquid waste products have been compiled. Legal aspects have also been taken into consideration and the potential for this type of fuel on the Swedish energy market has been evaluated. Today the supply of animal and vegetable based liquid waste products for energy production in Sweden is limited. The total production of animal based liquid fat is about 10,000 tonnes annually. The animal based liquid waste products origin mainly from the manufacturing of meat and bone meal. Since meat and bone meal has been banned from use in animal feeds it is possible that the amount of animal based liquid fat will decrease. The vegetable based liquid waste products that are produced in the processing of vegetable fats are today used mainly for internal energy production. This result in limited availability on the commercial market. The potential for import of animal and vegetable based liquid waste products is estimated to be relatively large since the production of this type of waste products is larger in many other countries compared to Sweden. Vegetable oils that are used as food or raw material in industries could also be imported for combustion, but this is not reasonable today since the energy prices are relatively low. Restrictions allow import of SRM exclusively from Denmark. This is today the only limit for increased imports of animal based liquid fat. The restrictions for handle and combustion of animal and vegetable based liquid waste products are partly unclear since this is covered in several regulations that are not easy to interpret. The new directive for combustion of waste (2000/76/EG) is valid for animal based waste products but not for cadaver or vegetable based waste products from provisions industries. This study has shown that more than 27,400 tonnes of animal based liquid waste products and about 6,000 tonnes of vegetable based liquid waste products were used for combustion in Sweden

Review: Utilization of Waste From Coffee Production

Science.gov (United States)

Blinová, Lenka; Sirotiak, Maroš; Bartošová, Alica; Soldán, Maroš

2017-06-01

Coffee is one of the most valuable primary products in the world trade, and also a central and popular part of our culture. However, coffees production generate a lot of coffee wastes and by-products, which, on the one hand, could be used for more applications (sorbent for the removal of heavy metals and dyes from aqueous solutions, production of fuel pellets or briquettes, substrate for biogas, bioethanol or biodiesel production, composting material, production of reusable cups, substrat for mushroom production, source of natural phenolic antioxidants etc.), but, on the other hand, it could be a source of severe contamination posing a serious environmental problem. In this paper, we present an overview of utilising the waste from coffee production.

Innovative technologies of waste recycling with production of high performance products

International Nuclear Information System (INIS)

Gilmanshin, R; Azimov, Yu I; Gilmanshina, S I; Ferenets, A V; Galeeva, A I

2015-01-01

The innovative ways of recycling wastes as a tool for sustainable development are presented in the article. The technology of the production of a composite material based on the rubber fiber composite waste tire industry is presented. The results of experimental use of the products in the real conditions. The comparative characteristics of the composite material rubber fiber composite are given. The production technology of construction and repairing materials on the basis of foamed glass is presented. (paper)

Innovative technologies of waste recycling with production of high performance products

Science.gov (United States)

Gilmanshin, R.; Ferenets, A. V.; Azimov, Yu I.; Galeeva, A. I.; Gilmanshina, S. I.

2015-06-01

The innovative ways of recycling wastes as a tool for sustainable development are presented in the article. The technology of the production of a composite material based on the rubber fiber composite waste tire industry is presented. The results of experimental use of the products in the real conditions. The comparative characteristics of the composite material rubber fiber composite are given. The production technology of construction and repairing materials on the basis of foamed glass is presented.

Opportunities, perspectives and limits in lactic acid production from waste and industrial by-products

Directory of Open Access Journals (Sweden)

Mladenović Dragana D.

2016-01-01

Full Text Available In line with the goals of sustainable development and environmental protection today great attention is directed towards new technologies for waste and industrial by-products utilization. Waste products represent potentially good raw material for production other valuable products, such as bioethanol, biogas, biodiesel, organic acids, enzymes, microbial biomass, etc. Since the first industrial production to the present, lactic acid has found wide application in food, cosmetic, pharmaceutical and chemical industries. In recent years, the demand for lactic acid has been increasing considerably owing to its potential use as a monomer for the production of poly-lactic acid (PLA polymers which are biodegradable and biocompatible with wide applications. Waste and industrial by-products such are whey, molasses, stillage, waste starch and lignocellulosic materials are a good source of fermentable sugars and many other substances of great importance for the growth of microorganisms, such as proteins, minerals and vitamins. Utilization of waste products for production of lactic acid could help to reduce the total cost of lactic acid production and except the economic viability of the process offers a solution of their disposal. Fermentation process depends on chemical and physical nature of feedstocks and the lactic acid producer. This review describes the characteristics, abilities and limits of microorganisms involved in lactic acid production, as well as the characteristics and types of waste products for lactic acid production. The fermentation methods that have been recently reported to improve lactic acid production are summarized and compared. In order to improve processes and productivity, fed-batch fermentation, fermentation with immobilized cell systems and mixed cultures and opportunities of open (non-sterilized fermentation have been investigated.

Continuous biohydrogen production from waste bread by anaerobic sludge.

Science.gov (United States)

Han, Wei; Huang, Jingang; Zhao, Hongting; Li, Yongfeng

2016-07-01

In this study, continuous biohydrogen production from waste bread by anaerobic sludge was performed. The waste bread was first hydrolyzed by the crude enzymes which were generated by Aspergillus awamori and Aspergillus oryzae via solid-state fermentation. It was observed that 49.78g/L glucose and 284.12mg/L free amino nitrogen could be produced with waste bread mass ratio of 15% (w/v). The waste bread hydrolysate was then used for biohydrogen production by anaerobic sludge in a continuous stirred tank reactor (CSTR). The optimal hydrogen production rate of 7.4L/(Ld) was achieved at chemical oxygen demand (COD) of 6000mg/L. According to the results obtained from this study, 1g waste bread could generate 0.332g glucose which could be further utilized to produce 109.5mL hydrogen. This is the first study which reports continuous biohydrogen production from waste bread by anaerobic sludge. Copyright © 2016 Elsevier Ltd. All rights reserved.

Qualification of R.A. waste conditioning process and installations by ONDRAF/NIRAS

International Nuclear Information System (INIS)

Havard, P.; Faniel, L.; Voet, M.; Goeyse, A. de.

1993-01-01

ONDRAF/NIRAS in its role of national agency responsible for the management of radioactive waste in Belgium (including transport, intermediate storage and final disposal of the conditioned waste) has defined and enforces conditions for the acceptance (i.e. taking over) of conditioned waste packages. The waste acceptance conditions applicable at the present time are: 1. The conditioning process and installations are qualified by ONDRAF/NIRAS; 2. The waste packages are produced according to the qualified process and installations, and meet the technical specifications and acceptance criteria defined by ONDRAF/NIRAS; 3. The production of the waste packages is supervised by ONDRAF/NIRAS through an inspection and control programme specific to each conditioning process and associated installation, and has been found satisfactory. (author)

Glass-ceramics: Their production from wastes - a review

Energy Technology Data Exchange (ETDEWEB)

Rawlings, R.D.; Wu, J.P.; Boccaccini, A.R. [University of London, London (United Kingdom). Imperial College of Science & Technology, Dept. of Medicine

2006-02-15

Glass-ceramics are polycrystalline materials of fine microstructure that are produced by the controlled crystallisation (devitrification) of a glass. Numerous silicate based wastes, such as coal combustion ash, slag from steel production, fly ash and filter dusts from waste incinerators, mud from metal hydrometallurgy, different types of sludge as well as glass cullet or mixtures of them have been considered for the production of glass-ceramics. Developments of glass-ceramics from waste using different processing methods are described comprehensively in this review, covering R&D work carried out worldwide in the last 40 years. Properties and applications of the different glass-ceramics produced are discussed. The review reveals that considerable knowledge and expertise has been accumulated on the process of transformation of silicate waste into useful glass-ceramic products. These glass-ceramics are attractive as building materials for usage as construction and architectural components or for other specialised technical applications requiring a combination of suitable thermo-mechanical properties. Previous attempts to commercialise glass-ceramics from waste and to scale-up production for industrial exploitation are also discussed.

Revaluation of Waste Yeast from Beer Production

Directory of Open Access Journals (Sweden)

Nicoleta Suruceanu

2013-11-01

Full Text Available Brewing yeast is an important waste product from beer production. The valorification of slurry yeast mainly consists of separation of vitamins and important nitrogen compounds. The hops compounds, one of the most important raw materials in beer technology are removed beforehand valorification. The prenylflavonoids compounds from hops are important bioactive compounds that can be revaluation with proper technology. Revaluation of prenylflavonoids from waste yeast into dietary supplement, identification and quantification of xanthohumol by HPLC method. Waste yeast from brewery pilot plant of USAMV Cluj Napoca it was dried by atomization and the powder was analyzed on xanthohumol content by HPLC method. For quantification a calibration curve it was used. The process of drying by atomisation lead to a powder product. It was used malt dextrin powder for stabilisation. The final product it was encapsulated. The xanthohumol content of powdered yeast it was 1.94 µg/ml. In conclusion the slurry yeast from beer production it is an important source of prenylflavonoids compounds.

[Influence of impurities on waste plastics pyrolysis: products and emissions].

Science.gov (United States)

Zhao, Lei; Wang, Zhong-Hui; Chen, De-Zhen; Ma, Xiao-Bo; Luan, Jian

2012-01-01

The study is aimed to evaluate the impact of impurities like food waste, paper, textile and especially soil on the pyrolysis of waste plastics. For this purpose, emissions, gas and liquid products from pyrolysis of waste plastics and impurities were studied, as well as the transfer of element N, Cl, S from the substrates to the pyrolysis products. It was found that the presence of food waste would reduce the heat value of pyrolysis oil to 27 MJ/kg and increase the moisture in the liquid products, therefore the food residue should be removed from waste plastics; and the soil, enhance the waste plastics' pyrolysis by improving the quality of gas and oil products. The presence of food residue, textile and paper leaded to higher gas emissions.

Polyhydroxyalkanoate (PHA) production from waste.

Science.gov (United States)

Rhu, D H; Lee, W H; Kim, J Y; Choi, E

2003-01-01

PHA (polyhydroxyalkanoate) production was attempted with SBRs from food waste. Seed microbes were collected from a sewage treatment plant with a biological nutrient removal process, and acclimated with synthetic substrate prior to the application of the fermented food waste. Laboratory SBRs were used to produce PHA with limited oxygen and nutrients. The maximum content of 51% PHA was obtained with an anaerobic/aerobic cycle with P limitation, and the yield was estimated to be about 0.05 gPHA(produced)/gCOD(applied) or 25 kg PHA/dry ton of food waste, assuming more than 40% of the PHA contents were recoverable. PHB/PHA ratios were 0.74 to 0.77 due to the higher acetate concentrations. Economical analysis seemed to suggest the PHA produced from the food waste could be an alternative material to produce the biodegradable plastic to be used for the collection bags for solid waste.

Method of processing liquid waste containing fission product

International Nuclear Information System (INIS)

Funabashi, Kiyomi; Kawamura, Fumio; Matsuda, Masami; Komori, Itaru; Miura, Eiichi.

1988-01-01

Purpose: To prepare solidification products of low surface dose by removing cesium which is main radioactive nuclides from re-processing plants. Method: Liquid wastes containing a great amount of fission products are generated accompanying the reprocessing for spent nuclear fuels. After pH adjustment, the liquid wastes are sent to a concentrator to concentrate the dissolved ingredients. The concentrated liquid wastes are pumped to an adsorption tower in which radioactive cesium contributing much to the surface dose is removed. Then, the liquid wastes are sent by way of a surge tank to a mixing tank, in which they are mixed under stirring with solidifying agents such as cements. Then, the mixture is filled in a drum-can and solidified. According to this invention, since radioactive cesium is removed before solidification, it is possible to prepare solidification products at low surface dose and facilitate the handling of the solidification products. (Horiuchi, T.)

Evaluation of the Acceptability of Potential Depleted Uranium Hexafluoride Conversion Products at the Envirocare Disposal Site

Energy Technology Data Exchange (ETDEWEB)

Croff, A.G.

2001-01-11

The purpose of this report is to review and document the capability of potential products of depleted UF{sub 6} conversion to meet the current waste acceptance criteria and other regulatory requirements for disposal at the facility in Clive, Utah, owned by Envirocare of Utah, Inc. The investigation was conducted by identifying issues potentially related to disposal of depleted uranium (DU) products at Envirocare and conducting an initial analysis of them. Discussions were then held with representatives of Envirocare, the state of Utah (which is a NRC Agreement State and, thus, is the cognizant regulatory authority for Envirocare), and DOE Oak Ridge Operations. Provisional issue resolution was then established based on the analysis and discussions and documented in a draft report. The draft report was then reviewed by those providing information and revisions were made, which resulted in this document. Issues that were examined for resolution were (1) license receipt limits for U isotopes; (2) DU product classification as Class A waste; (3) use of non-DOE disposal sites for disposal of DOE material; (4) historical NRC views; (5) definition of chemical reactivity; (6) presence of mobile radionuclides; and (7) National Environmental Policy Act coverage of disposal. The conclusion of this analysis is that an amendment to the Envirocare license issued on October 5, 2000, has reduced the uncertainties regarding disposal of the DU product at Envirocare to the point that they are now comparable with uncertainties associated with the disposal of the DU product at the Nevada Test Site that were discussed in an earlier report.

Public Acceptance of Low-Level Waste Disposal Critical to the Nuclear Renaissance

International Nuclear Information System (INIS)

Sonny Goldston, W.T.

2009-01-01

The disposal of various Low-Level Waste (LLW) forms projected to result from the operation of a pilot or large scale Advanced Fuel Cycle Initiative Programs' (formally known as Global Nuclear Energy Partnership (GNEP)) reprocessing and vitrification plants requires the DOE LLW program and regulatory structure to be utilized in its present form due to the limited availability of Nuclear Regulatory Commission licensed commercial LLW disposal facilities to handle wastes with radionuclide concentrations that are greater than Nuclear Regulatory Commission (NRC) Class A limits. This paper will describe the LLW forms and the regulatory structures and facilities available to dispose of this waste. Then the paper discusses the necessity of an excellent public involvement program to ensure the success of an effective technical solution. All of the decisions associated with the management of these wastes are of interest to the public and successful program implementation would be impossible without including the public up-front in the program formulation. Serious problems can result if program decisions are made without public involvement, and if the public is informed after key decisions are made. This paper will describe the regulatory and public involvement program and their effects on the decisions concerning the disposal of Low-Level Radioactive Waste (LLW) at the Savannah River Site (SRS). An extensive public communications effort resulted in endorsement of changes in disposal practices by the SRS Citizens Advisory Board that was critical to the success of the program. A recommendation will be made to install a public involvement program that is similar to the SRS Citizens Advisory Board in order to ensure the success of the AFCI programs in view of the limited availability to handle the wastes from the program and the public acceptance of change that will be required. (authors)

Eco-efficient waste glass recycling: Integrated waste management and green product development through LCA.

Science.gov (United States)

Blengini, Gian Andrea; Busto, Mirko; Fantoni, Moris; Fino, Debora

2012-05-01

As part of the EU Life + NOVEDI project, a new eco-efficient recycling route has been implemented to maximise resources and energy recovery from post-consumer waste glass, through integrated waste management and industrial production. Life cycle assessment (LCA) has been used to identify engineering solutions to sustainability during the development of green building products. The new process and the related LCA are framed within a meaningful case of industrial symbiosis, where multiple waste streams are utilised in a multi-output industrial process. The input is a mix of rejected waste glass from conventional container glass recycling and waste special glass such as monitor glass, bulbs and glass fibres. The green building product is a recycled foam glass (RFG) to be used in high efficiency thermally insulating and lightweight concrete. The environmental gains have been contrasted against induced impacts and improvements have been proposed. Recovered co-products, such as glass fragments/powders, plastics and metals, correspond to environmental gains that are higher than those related to landfill avoidance, whereas the latter is cancelled due to increased transportation distances. In accordance to an eco-efficiency principle, it has been highlighted that recourse to highly energy intensive recycling should be limited to waste that cannot be closed-loop recycled. Copyright © 2011 Elsevier Ltd. All rights reserved.

Characterization of wastes from fission 99 Mo production

International Nuclear Information System (INIS)

Endo, L.S.; Dellamano, J.C.

1992-07-01

This work is a preliminary study on waste-streams generated in a fission 99 Mo production plant, their characterization and quantification. The study is based on a plant whose 99 Mo production process is the alkaline dissolution of U-target. The target is made of 1 g of enriched 235 U, therefore most of radionuclides present in the waste-streams are fission products. All the radionuclides inventories were estimated based on ORIGEN-2 Code. The characterization was done as a primary stage for the establishment of waste management plan, which should be subject for further study. (author)

Passengers waste production during flights.

Science.gov (United States)

Tofalli, Niki; Loizia, Pantelitsa; Zorpas, Antonis A

2017-12-20

We assume that during flights the amount of waste that is produced is limited. However, daily, approximately 8000 commercial airplanes fly above Europe's airspace while at the same time, more than 17,000 commercial flights exist in the entire world. Using primary data from airlines, which use the Larnaca's International Airport (LIA) in Cyprus, we have tried to understand why wastes are produced during a typical flight such as food waste, paper, and plastics, as well as how passengers affect the production of those wastes. The compositional analysis took place on 27 flights of 4 different airlines which used LIA as final destination. The evaluation indicated that the passenger's habits and ethics, and the policy of each airline produced different kinds of waste during the flights and especially food waste (FW). Furthermore, it was observed that the only waste management strategy that exists in place in the airport is the collection and the transportation of all those wastes from aircrafts and from the airport in the central unit for further treatment. Hence, this research indicated extremely difficulties to implement any specific waste minimization, or prevention practice or other sorting methods during the flights due to the limited time of the most flights (less than 3 h), the limited available space within the aircrafts, and the strictly safety roles that exist during the flights.

Waste incineration

International Nuclear Information System (INIS)

Rumplmayr, A.; Sammer, G.

2001-01-01

Waste incineration can be defined as the thermal conversion processing of solid waste by chemical oxidation. The types of wastes range from solid household waste and infectious hospital waste through to toxic solid, liquid and gaseous chemical wastes. End products include hot incineration gases, composed primarily of nitrogen, carbon dioxide, water vapor and to a smaller extend of non-combustible residue (ash) and air pollutants (e. g. NO x ). Energy can be recovered by heat exchange from the hot incineration gases, thus lowering fossil fuel consumption that in turn can reduce emissions of greenhouse gases. Burning of solid waste can fulfil up to four distinctive objectives (Pera, 2000): 1. Volume reduction: volume reduction of about 90 %, weight reduction of about 70 %; 2. Stabilization of waste: oxidation of organic input; 3. Recovery of energy from waste; 4. Sanitization of waste: destruction of pathogens. Waste incineration is not a means to make waste disappear. It does entail emissions into air as well as water and soil. The generated solid residues are the topic of this task force. Unlike other industrial processes discussed in this platform, waste incineration is not a production process, and is therefore not generating by-products, only residues. Residues that are isolated from e. g. flue gas, are concentrated in another place and form (e. g. air pollution control residues). Hence, there are generally two groups of residues that have to be taken into consideration: residues generated in the actual incineration process and others generated in the flue gas cleaning system. Should waste incineration finally gain public acceptance, it will be necessary to find consistent regulations for both sorts of residues. In some countries waste incineration is seen as the best option for the treatment of waste, whereas in other countries it is seen very negative. (author)

A revised oceanographic model to calculate the limiting capacity of the ocean to accept radioactive waste

International Nuclear Information System (INIS)

Webb, G.A.M.; Grimwood, P.D.

1976-12-01

This report describes an oceanographic model which has been developed for the use in calculating the capacity of the oceans to accept radioactive wastes. One component is a relatively short-term diffusion model which is based on that described in an earlier report (Webb et al., NRPB-R14(1973)), but which has been generalised to some extent. Another component is a compartment model which is used to calculate long-term widespread water concentrations. This addition overcomes some of the short comings of the earlier diffusion model. Incorporation of radioactivity into deep ocean sediments is included in this long-term model as a removal mechanism. The combined model is used to provide a conservative (safe) estimate of the maximum concentrations of radioactivity in water as a function of time after the start of a continuous disposal operation. These results can then be used to assess the limiting capacity of an ocean to accept radioactive waste. (author)

Application of the coal-mining waste in building ceramics production

Directory of Open Access Journals (Sweden)

Vaysman Yakov Iosifovich

Full Text Available In the process of construction ceramics production a substantial quantity of non-renewable natural resources - clays - are used. One of the ways of science development in building materials production is investigation of the possibility of regular materials production using technogenic waste. Application of coal-mining waste (technogenic raw material in charge composition for production of ceramic products provides rational use of fuel, contributes to implementation of resource saving technologies on construction materials production enterprises. Though science development on revealing new raw material sources should be conducted with account for safety, reliability, technical, ecological and economical sides of the problem, which is especially current. The article deals with the problem of coal-mining waste usage in building ceramics production instead of fresh primary component (clay, fluxes, thinning agents and combustible additives. The interdependence between the density and shrinkage of the ceramic products and the amount and quality of coal-mining waste in its composition was established. The optimal proportion of coal-mining waste and clay in building ceramics production was estimated.

Immobilization of fission products in phosphate ceramic waste forms

International Nuclear Information System (INIS)

Singh, D.

1996-01-01

The goal of this project is to develop and demonstrate the feasibility of a novel low-temperature solidification/stabilization (S/S) technology for immobilizing waste streams containing fission products such as cesium, strontium, and technetium in a chemically bonded phosphate ceramic. This technology can immobilize partitioned tank wastes and decontaminate waste streams containing volatile fission products

Cleaner production for solid waste management in leather industry ...

African Journals Online (AJOL)

Cleaner production for solid waste management in leather industry. ... From the processes, wastes are generated which include wastewater effluents, solid wastes, and hazardous wastes. In developing countries including Ethiopia, many ... The solid waste inventory of the factory has been carried out. The major problems ...

Waste volume reduction by spray drying

Energy Technology Data Exchange (ETDEWEB)

Toscano, Rodrigo A.; Tello, Clédola C. O. de, E-mail: Rodrigotoscano1@gmail.com, E-mail: tellocc@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

The operation of nuclear facilities generates liquid wastes which require treatment to control the chemical compounds and removal of radioactive contaminants. These wastes can come from the cooling of the primary reactor system, from the reactor pool decontamination, washing of contaminated clothing, among others. The ion exchange resin constitutes the largest fraction of this waste, classified as low and intermediate level of radiation. According to CNEN Standard 8.01, the minimization of the volume and activity of the radioactive waste generated in the operation of a nuclear installation, radiative installation, industrial mining installation or radioactive waste deposit should be ensured. In addition, one of the acceptance criteria for wastes in repositories required by CNEN NN 6.09 is that it be solid or solidified. Thus, these wastes must be reduced in volume and solidified to meet the standards and the safety of the population and the environment. The objective of this work is to find a solution that associates the least generation of packaged waste and the acceptance criteria of waste for the deposition in the national repository. This work presents a proposal of reduction of the volume of the liquid wastes generated by nuclear facilities by drying by for reduction of volume for a greater incorporation of wastes in cement. Using spray dryer, an 18% reduction in the production of cemented waste products was observed in relation to the method currently used with compressive strength measurement above the standard, and it is believed that this value may increase in future tests. (author)

Waste volume reduction by spray drying

International Nuclear Information System (INIS)

Toscano, Rodrigo A.; Tello, Clédola C. O. de

2017-01-01

The operation of nuclear facilities generates liquid wastes which require treatment to control the chemical compounds and removal of radioactive contaminants. These wastes can come from the cooling of the primary reactor system, from the reactor pool decontamination, washing of contaminated clothing, among others. The ion exchange resin constitutes the largest fraction of this waste, classified as low and intermediate level of radiation. According to CNEN Standard 8.01, the minimization of the volume and activity of the radioactive waste generated in the operation of a nuclear installation, radiative installation, industrial mining installation or radioactive waste deposit should be ensured. In addition, one of the acceptance criteria for wastes in repositories required by CNEN NN 6.09 is that it be solid or solidified. Thus, these wastes must be reduced in volume and solidified to meet the standards and the safety of the population and the environment. The objective of this work is to find a solution that associates the least generation of packaged waste and the acceptance criteria of waste for the deposition in the national repository. This work presents a proposal of reduction of the volume of the liquid wastes generated by nuclear facilities by drying by for reduction of volume for a greater incorporation of wastes in cement. Using spray dryer, an 18% reduction in the production of cemented waste products was observed in relation to the method currently used with compressive strength measurement above the standard, and it is believed that this value may increase in future tests. (author)

Konrad transport study: Safety analysis of the transportation of radioactive waste to the Konrad waste disposal site

International Nuclear Information System (INIS)

Lange, F.; Gruendler, D.; Schwarz, G.

1992-05-01

For the purpose of the study the anticipated waste transport volume and the waste properties were analysed in detail. This included information on the transport containers, waste product properties, activity inventories and local dose rates of the waste packages being transported. The envisaged practical implementation, i.e. the transport arrangements including shunting operations at the Braunschweig marshalling yard and the Beddingen interchange station, were also included. The two shipping scenarios 100% transportation by rail and 80% transportation by rail, 20% by road, which could be considered to bound the real conditions, were analysed. The relevant transport regulations contain the requirements to be met by the transport of shipping units carrying radioactive waste. In addition, the ''Konrad preliminary waste acceptance criteria'' contain activity limits for waste packages being disposed of in conjunction with further requirements relating to the properties of waste products and waste containers. (orig./DG)

Characterization of the Defense Waste Processing Facility (DWPF) Environmental Assessment (EA) glass Standard Reference Material. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Jantzen, C.M.; Bibler, N.E.; Beam, D.C.; Crawford, C.L.; Pickett, M.A.

1993-06-01

Liquid high-level nuclear waste at the Savannah River Site (SRS) will be immobilized by vitrification in borosilicate glass. The glass will be produced and poured into stainless steel canisters in the Defense Waste Processing Facility (DWPF). Other waste form producers, such as West Valley Nuclear Services (WVNS) and the Hanford Waste Vitrification Project (HWVP), will also immobilize high-level radioactive waste in borosilicate glass. The canistered waste will be stored temporarily at each facility for eventual permanent disposal in a geologic repository. The Department of Energy has defined a set of requirements for the canistered waste forms, the Waste Acceptance Product Specifications (WAPS). The current Waste Acceptance Primary Specification (WAPS) 1.3, the product consistency specification, requires the waste form producers to demonstrate control of the consistency of the final waste form using a crushed glass durability test, the Product Consistency Test (PCI). In order to be acceptable, a waste glass must be more durable during PCT analysis than the waste glass identified in the DWPF Environmental Assessment (EA). In order to supply all the waste form producers with the same standard benchmark glass, 1000 pounds of the EA glass was fabricated. The chemical analyses and characterization of the benchmark EA glass are reported. This material is now available to act as a durability and/or redox Standard Reference Material (SRM) for all waste form producers.

Wastes from bioethanol and beer productions as substrates for l(+) lactic acid production - A comparative study.

Science.gov (United States)

Djukić-Vuković, Aleksandra; Mladenović, Dragana; Radosavljević, Miloš; Kocić-Tanackov, Sunčica; Pejin, Jelena; Mojović, Ljiljana

2016-02-01

Waste substrates from bioethanol and beer productions are cheap, abundant and renewable substrates for biorefinery production of lactic acid (LA) and variability in their chemical composition presents a challenge in their valorisation. Three types of waste substrates, wasted bread and wasted potato stillage from bioethanol production and brewers' spent grain hydrolysate from beer production were studied as substrates for the production of l(+) LA and probiotic biomass by Lactobacillus rhamnosus ATCC 7469. The correlation of the content of free alpha amino nitrogen and the production of LA was determined as a critical characteristic of the waste media for efficient LA production by L. rhamnosus on the substrates which contained equal amount of fermentable sugars. A maximal LA productivity of 1.54gL(-1)h(-1) was obtained on wasted bread stillage media, whilst maximal productivities achieved on the potato stillage and brewers' spent grain hydrolysate media were 1.28gL(-1)h(-1)and 0.48gL(-1)h(-1), respectively. A highest LA yield of 0.91gg(-1) was achieved on wasted bread stillage media, followed by the yield of 0.81gg(-1) on wasted potato stillage and 0.34gg(-1) on brewers' spent grain hydrolysate media. The kinetics of sugar consumption in the two stillage substrates were similar while the sugar conversion in brewers' spent grain hydrolysate was slower and less efficient due to significantly lower content of free alpha amino nitrogen. The lignocellulosic hydrolysate from beer production required additional supplementation with nitrogen. Copyright © 2015 Elsevier Ltd. All rights reserved.

Co-digestion of municipal sludge and external organic wastes for enhanced biogas production under realistic plant constraints.

Science.gov (United States)

Tandukar, Madan; Pavlostathis, Spyros G

2015-12-15

A bench-scale investigation was conducted to select external organic wastes and mixing ratios for co-digestion with municipal sludge at the F. Wayne Hill Water Resources Center (FWHWRC), Gwinnett County, GA, USA to support a combined heat and power (CHP) project. External wastes were chosen and used subject to two constraints: a) digester retention time no lower than 15 d; and b) total biogas (methane) production not to exceed a specific target level based on air permit constraints on CO2 emissions. Primary sludge (PS), thickened waste activated sludge (TWAS) and digested sludge collected at the FWHWRC, industrial liquid waste obtained from a chewing gum manufacturing plant (GW) and dewatered fat-oil-grease (FOG) were used. All sludge and waste samples were characterized and their ultimate digestibility was assessed at 35 °C. The ultimate COD to methane conversion of PS, TWAS, municipal sludge (PS + TWAS; 40:60 w/w TS basis), GW and FOG was 49.2, 35.2, 40.3, 72.7, and 81.1%, respectively. Co-digestion of municipal sludge with GW, FOG or both, was evaluated using four bench-scale, mesophilic (35 °C) digesters. Biogas production increased significantly and additional degradation of the municipal sludge between 1.1 and 30.7% was observed. Biogas and methane production was very close to the target levels necessary to close the energy deficit at the FWHWRC. Co-digestion resulted in an effluent quality similar to that of the control digester fed only with the municipal sludge, indicating that co-digestion had no adverse effects. Study results prove that high methane production is achievable with the addition of concentrated external organic wastes to municipal digesters, at acceptable higher digester organic loadings and lower retention times, allowing the effective implementation of CHP programs at municipal wastewater treatment plants, with significant cost savings. Copyright © 2015 Elsevier Ltd. All rights reserved.

Final waste classification and waste form technical position papers

International Nuclear Information System (INIS)

1983-05-01

The waste classification technical position paper describes overall procedures acceptable to NRC staff which may be used by licensees to determine the presence and concentrations of the radionuclides listed in section 61.55, and thereby classifying waste for near-surface disposal. This technical position paper also provides guidance on the types of information which should be included in shipment manifests accompanying waste shipments to near-surface disposal facilities. The technical position paper on waste form provides guidance to waste generators on test methods and results acceptable to NRC staff for implementing the 10 CFR Part 61 waste form requirements. It can be used as an acceptable approach for demonstrating compliance with the 10 CFR Part 61 waste structural stability criteria. This technical position paper includes guidance on processing waste into an acceptable stable form, designing acceptable high-integrity containers, packaging cartridge filters, and minimizing radiation effects on organic ion-exchange resins. The guidance in the waste form technical position paper may be used by licensees as the basis for qualifying process control programs to meet the waste form stability requirements, including tests which can be used to demonstrate resistance to degradation arising from the effects of compression, moisture, microbial activity, radiation, and chemical changes. Generic test data (e.g., topical reports prepared by vendors who market solidification technology) may be used for process control program qualification where such generic data is applicable to the particular types of waste generated by a licensee

The influence of slaughterhouse waste on fermentative H2 production from food waste: Preliminary results

International Nuclear Information System (INIS)

Boni, Maria Rosaria; Sbaffoni, Silvia; Tuccinardi, Letizia

2013-01-01

Highlights: • Co-digestion process finalized to bio-H 2 production was tested in batch tests. • Slaughterhouse waste (SHW) and food waste (FW) were co-digested in different proportions. • The presence of SHW affected the H 2 production from FW. • When SHW ranging between 50% and 70% the H 2 production is improved. • SHW percentages above 70%, led to a depletion in H 2 production. - Abstract: The aim of this study was to evaluate the influence of slaughterhouse waste (SHW; essentially the skin, fats, and meat waste of pork, poultry, and beef) in a fermentative co-digestion process for H 2 production from pre-selected organic waste taken from a refectory (food waste [FW]). Batch tests under mesophilic conditions were conducted in stirred reactors filled with different proportions of FW and SHW. The addition of 60% and 70% SHW to a mixture of SHW and FW improved H 2 production compared to that in FW only, reaching H 2 -production yields of 145 and 109 ml gVS 0 -1 , respectively, which are 1.5–2 times higher than that obtained with FW alone. Although the SHW ensured a more stable fermentative process due to its high buffering capacity, a depletion of H 2 production occurred when SHW fraction was higher than 70%. Above this percentage, the formation of foam and aggregated material created non-homogenous conditions of digestion. Additionally, the increasing amount of SHW in the reactors may lead to an accumulation of long chain fatty acids (LCFAs), which are potentially toxic for anaerobic microorganisms and may inhibit the normal evolution of the fermentative process

Radioactive waste and public acceptance

International Nuclear Information System (INIS)

Perkins, B.

1977-01-01

Radioactive waste just happens to be the major issue in the public eye now--it could be replaced by another issue later. A survey is quoted to prove that wastes are not really one of the burning national issues of the day. The people opposing the nuclear program cannot be said to represent the public. The taste of the press for the melodramatic is pointed out. The issue needs to be presented with the proper perspective, in the context of the benefits and risks of nuclear power

Production of surfactin by bacillus subtilis mtcc 2423 from waste frying oils

Directory of Open Access Journals (Sweden)

N. Vedaraman

2011-06-01

Full Text Available One of the obstacles in the way of wide scale industrial application of biosurfactants is the high production cost coupled with a low production rate. In order to lower the production cost surfactin production by Bacillus subtilis MTCC 2423 was studied in submerged batch cultivation using waste frying oils. It was observed that the decrease in surface tension was 56.32%, 48.5% and 46.1% with glucose, waste frying sunflower oil and waste frying rice bran oil, respectively. Biomass formation was 4.36 g/L, 3.67 g/L and 4.67 g/L for glucose, waste frying sunflower oil and waste frying rice bran oil, respectively. Product yield (g product/g substrate was 2.1%, 1.49% and 1.1% with glucose, waste frying sunflower oil and waste frying rice bran oil as substrates. This process facilitates safe disposal of waste frying oil, as well reducing the production cost of surfactin.

24 CFR 3282.360 - PIA acceptance of product certification programs or listings.

Science.gov (United States)

2010-04-01

... ENFORCEMENT REGULATIONS Primary Inspection Agencies § 3282.360 PIA acceptance of product certification... 24 Housing and Urban Development 5 2010-04-01 2010-04-01 false PIA acceptance of product certification programs or listings. 3282.360 Section 3282.360 Housing and Urban Development Regulations Relating...

Glass Ceramic Waste Forms for Combined CS+LN+TM Fission Products Waste Streams

International Nuclear Information System (INIS)

Crum, Jarrod V.; Turo, Laura A.; Riley, Brian J.; Tang, Ming; Kossoy, Anna; Sickafus, Kurt E.

2010-01-01

In this study, glass ceramics were explored as an alternative waste form for glass, the current baseline, to be used for immobilizing alkaline/alkaline earth + lanthanide (CS+LN) or CS+LN+transition metal (TM) fission-product waste streams generated by a uranium extraction (UREX+) aqueous separations type process. Results from past work on a glass waste form for the combined CS+LN waste streams showed that as waste loading increased, large fractions of crystalline phases precipitated upon slow cooling.(1) The crystalline phases had no noticeable impact on the waste form performance by the 7-day product consistency test (PCT). These results point towards the development of a glass ceramic waste form for treating CS+LN or CS+LN+TM combined waste streams. Three main benefits for exploring glass ceramics are: (1) Glass ceramics offer increased solubility of troublesome components in crystalline phases as compared to glass, leading to increased waste loading; (2) The crystalline network formed in the glass ceramic results in higher heat tolerance than glass; and (3) These glass ceramics are designed to be processed by the same melter technology as the current baseline glass waste form. It will only require adding controlled canister cooling for crystallization into a glass ceramic waste form. Highly annealed waste form (essentially crack free) with up to 50X lower surface area than a typical High-Level Waste (HLW) glass canister. Lower surface area translates directly into increased durability. This was the first full year of exploring glass ceramics for the Option 1 and 2 combined waste stream options. This work has shown that dramatic increases in waste loading are achievable by designing a glass ceramic waste form as an alternative to glass. Table S1 shows the upper limits for heat, waste loading (based on solubility), and the decay time needed before treatment can occur for glass and glass ceramic waste forms. The improvements are significant for both combined waste

Glass Ceramic Waste Forms for Combined CS+LN+TM Fission Products Waste Streams

Energy Technology Data Exchange (ETDEWEB)

Crum, Jarrod V.; Turo, Laura A.; Riley, Brian J.; Tang, Ming; Kossoy, Anna; Sickafus, Kurt E.

2010-09-23

In this study, glass ceramics were explored as an alternative waste form for glass, the current baseline, to be used for immobilizing alkaline/alkaline earth + lanthanide (CS+LN) or CS+LN+transition metal (TM) fission-product waste streams generated by a uranium extraction (UREX+) aqueous separations type process. Results from past work on a glass waste form for the combined CS+LN waste streams showed that as waste loading increased, large fractions of crystalline phases precipitated upon slow cooling.[1] The crystalline phases had no noticeable impact on the waste form performance by the 7-day product consistency test (PCT). These results point towards the development of a glass ceramic waste form for treating CS+LN or CS+LN+TM combined waste streams. Three main benefits for exploring glass ceramics are: (1) Glass ceramics offer increased solubility of troublesome components in crystalline phases as compared to glass, leading to increased waste loading; (2) The crystalline network formed in the glass ceramic results in higher heat tolerance than glass; and (3) These glass ceramics are designed to be processed by the same melter technology as the current baseline glass waste form. It will only require adding controlled canister cooling for crystallization into a glass ceramic waste form. Highly annealed waste form (essentially crack free) with up to 50X lower surface area than a typical High-Level Waste (HLW) glass canister. Lower surface area translates directly into increased durability. This was the first full year of exploring glass ceramics for the Option 1 and 2 combined waste stream options. This work has shown that dramatic increases in waste loading are achievable by designing a glass ceramic waste form as an alternative to glass. Table S1 shows the upper limits for heat, waste loading (based on solubility), and the decay time needed before treatment can occur for glass and glass ceramic waste forms. The improvements are significant for both combined waste

Exploitation of Food Industry Waste for High-Value Products.

Science.gov (United States)

Ravindran, Rajeev; Jaiswal, Amit K

2016-01-01

A growing global population leads to an increasing demand for food production and the processing industry associated with it and consequently the generation of large amounts of food waste. This problem is intensified due to slow progress in the development of effective waste management strategies and measures for the proper treatment and disposal of waste. Food waste is a reservoir of complex carbohydrates, proteins, lipids, and nutraceuticals and can form the raw materials for commercially important metabolites. The current legislation on food waste treatment prioritises the prevention of waste generation and least emphasises disposal. Recent valorisation studies for food supply chain waste opens avenues to the production of biofuels, enzymes, bioactive compounds, biodegradable plastics, and nanoparticles among many other molecules. Copyright © 2015 Elsevier Ltd. All rights reserved.

Verification of product quality from process control

International Nuclear Information System (INIS)

Drobot, A.; Bunnell, L.R.; Freeborn, W.P.; Macedo, P.B.; Mellinger, G.B.; Pegg, I.L.; Piepel, G.F.; Reimus, M.A.H.; Routt, K.R.; Saad, E.

1989-01-01

Process models were developed to characterize the waste vitrification at West Valley, in terms of process operating constraints and glass compositions achievable. The need for verification of compliance with the proposed Waste Acceptance Preliminary Specification criteria led to development of product models, the most critical one being a glass durability model. Both process and product models were used in developing a target composition for the waste glass. This target composition designed to ensure that glasses made to this target will be of acceptable durability after all process variations have been accounted for. 4 refs., 11 figs., 5 tabs

Formulation of a candidate glass for use as an acceptance test standard material

International Nuclear Information System (INIS)

Ebert, W.L.; Strachan, D.M.; Wolf, S.F.

1998-04-01

In this report, the authors discuss the formulation of a glass that will be used in a laboratory testing program designed to measure the precision of test methods identified in the privatization contracts for the immobilization of Hanford low-activity wastes. Tests will be conducted with that glass to measure the reproducibility of tests and analyses that must be performed by glass producers as a part of the product acceptance procedure. Test results will be used to determine if the contractually required tests and analyses are adequate for evaluating the acceptability of likely immobilized low-activity waste (ILAW) products. They will also be used to evaluate if the glass designed for use in these tests can be used as an analytical standard test material for verifying results reported by vendors for tests withg ILAW products. The results of those tests and analyses will be presented in a separate report. The purpose of this report is to document the strategy used to formulate the glass to be used in the testing program. The low-activity waste reference glass LRM that will be used in the testing program was formulated to be compositionally similar to ILAW products to be made with wastes from Hanford. Since the ILAW product compositions have not been disclosed by the vendors participating in the Hanford privatization project, the composition of LRM was formulated based on simulated Hanford waste stream and amounts of added glass forming chemicals typical for vitrified waste forms. The major components are 54 mass % SiO 2 , 20 mass % Na 2 O, 10 mass % Al 2 O 3 , 8 mass % B 2 O 3 , and 1.5 mass % K 2 O. Small amounts of other chemicals not present in Hanford wastes were also included in the glass, since they may be included as chemical additives in ILAW products. This was done so that the use of LRM as a composition standard could be evaluated. Radionuclides were not included in LRM because a nonradioactive material was desired

Nuclear wastes: end product or just the end

International Nuclear Information System (INIS)

Anon.

1977-01-01

Until the nuclear fuel cycle is closed, nuclear power plants will operate at an economic disadvantage relative to fossil-fuel plants. Although eight new reprocessing plants for spent fuel are needed by 1980 to deal with the wastes that are accumulating, public reaction to nuclear wastes and the threat of plutonium proliferation has halted this portion of the cycle and required expanded storage facilities. ERDA expects to have a way to package wastes by 1978, but is still looking for an acceptable place for permanent storage. Public concerns center on the fear that levels of radioactivity will affect present and future generations and the fear that some plutonium will be diverted for use in weapons. These fears are examined and not found to be warranted as long as zero radiation and total safeguards are not the required goal

Bioconversion of chicken wastes to value-added products

Energy Technology Data Exchange (ETDEWEB)

Barik, S; Forgacs, T; Isbister, J [ARCTECH, Inc., Alexandria, VA (United States)

1991-01-01

Increasing quantities of chicken waste concerns the poultry industry because of escalating disposal costs and the potential for environmental pollution. Biological conversion of these wastes to valuable products such as methane and/or chemical feed-stocks appears to be feasible. Biomethanation of chicken waste by a sewage sludge microbial consortium produced as much as 69 mol% methane in the gas phase. Acetic and propionic acids were the major acids produced during the bioconversion. Addition of chelating agents and other micro-nutrients enhanced methane production and shifted the ratios of intermediates accumulated. Preliminary data indicate that more than 60% of the chicken waste carbon was converted and that the nitrogen-rich residue may have potential as a soil additive. (author).

Consumption and production waste: another externality of tobacco use.

Science.gov (United States)

Novotny, T E; Zhao, F

1999-01-01

To describe the waste produced by and environmental implications of individual cigarette consumption (filter tips, packages, and cartons) and tobacco manufacturing. All available articles and reports published since 1970 related to cigarette consumption and production waste were reviewed. Global cigarette consumption data were used to estimate cigarette butt and packaging waste quantities. Data from the Center for Marine Conservation's International Coastal Cleanup Project were used to describe some environmental impacts of tobacco-related trash. Data from the United States Environmental Protection Agency's (EPA's) Toxics Release Inventory and reported global cigarette consumption totals were used to estimate waste production from cigarette manufacturing. In 1995, an estimated 5.535 trillion cigarettes (27,675 million cartons and 276,753 million packages) were sold by the tobacco industry globally. Some of the wastes from these products were properly deposited, but a large amount of tobacco consumption waste ends up in the environment. Some is recovered during environmental clean-up days. For the past eight years (1990-1997), cigarette butts have been the leading item found during the International Coastal Cleanup Project; they accounted for 19.1% of all items collected in 1997. The tobacco manufacturing process produces liquid, solid, and airborne waste. Among those wastes, some materials, including nicotine, are designated by the EPA as Toxics Release Inventory (TRI) chemicals. These are possible environmental health hazards. In 1995, the global tobacco industry produced an estimated 2262 million kilograms of manufacturing waste and 209 million kilograms of chemical waste. In addition, total nicotine waste produced in the manufacture of reduced nicotine cigarettes was estimated at 300 million kilograms. Laws against littering relative to cigarette butts could be better enforced. Additional taxes might be levied on cigarette products that would then be directed to

Production of Enzymes From Agricultural Wastes and Their Potential Industrial Applications.

Science.gov (United States)

Bharathiraja, S; Suriya, J; Krishnan, M; Manivasagan, P; Kim, S-K

Enzymatic hydrolysis is the significant technique for the conversion of agricultural wastes into valuable products. Agroindustrial wastes such as rice bran, wheat bran, wheat straw, sugarcane bagasse, and corncob are cheapest and plentifully available natural carbon sources for the production of industrially important enzymes. Innumerable enzymes that have numerous applications in industrial processes for food, drug, textile, and dye use have been produced from different types of microorganisms from agricultural wastes. Utilization of agricultural wastes offers great potential for reducing the production cost and increasing the use of enzymes for industrial purposes. This chapter focuses on economic production of actinobacterial enzymes from agricultural wastes to make a better alternative for utilization of biomass generated in million tons as waste annually. © 2017 Elsevier Inc. All rights reserved.

Waste analysis plan for the low-level burial grounds. Revision 2

International Nuclear Information System (INIS)

Pratt, D.A.

1997-01-01

The purpose of this waste analysis plan (WAP) is to document the waste 5 acceptance process, sampling methodologies, analytical techniques, and overall 6 processes that are undertaken for waste accepted for disposal at the Low-Level 7 Burial Grounds (LLBG), which are located in the 200 East and 200 West Areas of 8 the Hanford Facility, Richland, Washington. Because dangerous waste does not 9 include the source, special nuclear, and by-product material components of 10 mixed waste, radionuclides are not within the scope of this documentation. 11 The information on radionuclides is provided only for general knowledge. The 12 LLBG also receive low-level radioactive waste for disposal. The requirements 13 of this WAP are not applicable to this low-level waste

Prevention and minimization of waste production

International Nuclear Information System (INIS)

Noynaert, L.

1998-01-01

The main objective of the program Prevention and Minimization of Waste Production at the Belgian Nuclear Research Centre SCK/CEN is to contribute to reducing the volume and costs of nuclear waste. In addition, it aims to provide reliable data and models to the design engineers with a view to determining the final plant characteristics. Main activities in 1997 are described

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

CERN Multimedia

HSE Unit

2013-01-01

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

Bacterial Cellulose Production from Industrial Waste and by-Product Streams.

Science.gov (United States)

Tsouko, Erminda; Kourmentza, Constantina; Ladakis, Dimitrios; Kopsahelis, Nikolaos; Mandala, Ioanna; Papanikolaou, Seraphim; Paloukis, Fotis; Alves, Vitor; Koutinas, Apostolis

2015-07-01

The utilization of fermentation media derived from waste and by-product streams from biodiesel and confectionery industries could lead to highly efficient production of bacterial cellulose. Batch fermentations with the bacterial strain Komagataeibacter sucrofermentans DSM (Deutsche Sammlung von Mikroorganismen) 15973 were initially carried out in synthetic media using commercial sugars and crude glycerol. The highest bacterial cellulose concentration was achieved when crude glycerol (3.2 g/L) and commercial sucrose (4.9 g/L) were used. The combination of crude glycerol and sunflower meal hydrolysates as the sole fermentation media resulted in bacterial cellulose production of 13.3 g/L. Similar results (13 g/L) were obtained when flour-rich hydrolysates produced from confectionery industry waste streams were used. The properties of bacterial celluloses developed when different fermentation media were used showed water holding capacities of 102-138 g · water/g · dry bacterial cellulose, viscosities of 4.7-9.3 dL/g, degree of polymerization of 1889.1-2672.8, stress at break of 72.3-139.5 MPa and Young's modulus of 0.97-1.64 GPa. This study demonstrated that by-product streams from the biodiesel industry and waste streams from confectionery industries could be used as the sole sources of nutrients for the production of bacterial cellulose with similar properties as those produced with commercial sources of nutrients.

Equilibrium Temperature Profiles within Fission Product Waste Forms

Energy Technology Data Exchange (ETDEWEB)

Kaminski, Michael D. [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-10-01

We studied waste form strategies for advanced fuel cycle schemes. Several options were considered for three waste streams with the following fission products: cesium and strontium, transition metals, and lanthanides. These three waste streams may be combined or disposed separately. The decay of several isotopes will generate heat that must be accommodated by the waste form, and this heat will affect the waste loadings. To help make an informed decision on the best option, we present computational data on the equilibrium temperature of glass waste forms containing a combination of these three streams.

Method of processing solidification product of radioactive waste

International Nuclear Information System (INIS)

Daime, Fumiyoshi.

1988-01-01

Purpose: To improve the long-time stability of solidification products by providing solidification products with liquid tightness, gas tightness, abrasion resistance, etc., of the products in the course of the solidification for the treatment of radioactive wastes. Method: The surface of solidification products prepared by mixing solidifying agents with powder or pellets is entirely covered with high molecular polymer such as epoxy resin. The epoxy resin has excellent properties such as radiation-resistance, heat resistance, water proofness and chemical resistance, as well as have satisfactory mechanical properties. This can completely isolate the solidification products of radioactive wastes from the surrounding atmosphere. (Yoshino, Y.)

Projected radionuclide inventories of DWPF glass from current waste at time of production

International Nuclear Information System (INIS)

Plodinec, M.J.

1993-01-01

The Waste Acceptance Preliminary Specifications (WAPS) require that the DWPF estimate the inventory of long-lived radionuclides present in the waste glass, and report the values in the Waste Form Qualification Report. In this report, conservative (biased high) estimates of the radionuclide inventory of glass produced from waste currently in the Tank Farm are provided. In most cases, these calculated values compare favorably with actual data. In those cases where the agreement is not good, the values reported here are conservative

Assessment of application of selected waste for production of biogas

Science.gov (United States)

Pawlita-Posmyk, Monika; Wzorek, Małgorzata

2017-10-01

Recently, the idea of biogas production has become a popular topic in Poland. Biogas is a valuable source of renewable energy with a potential application in electricity and heat production. Numerous types of technological solutions of biogas production are closely linked to the availability of substrates in the area, as well as their quantity and their properties. The paper presents the assessment of application in biogas production selected wastes such as communal and household sewage sludge and waste from a paper production in Opole region (Poland). The annual productions of methane, biogas and electricity were estimated. Chosen physico-chemical properties important in fermentation process were taken into consideration in the assessment. The highest value of potential energy was obtained using waste from the paper industry but the most appropriate parameters for this process has sewage sludge from the municipal sewage treatment plant. The use of sewage sludge from domestic and municipal sewage and waste from the paper industry creates the opportunity to reduce the amount of waste materials.

Projected Salt Waste Production from a Commercial Pyroprocessing Facility

Directory of Open Access Journals (Sweden)

Michael F. Simpson

2013-01-01

Full Text Available Pyroprocessing of used nuclear fuel inevitably produces salt waste from electrorefining and/or oxide reduction unit operations. Various process design characteristics can affect the actual mass of such waste produced. This paper examines both oxide and metal fuel treatment, estimates the amount of salt waste generated, and assesses potential benefit of process options to mitigate the generation of salt waste. For reference purposes, a facility is considered in which 100 MT/year of fuel is processed. Salt waste estimates range from 8 to 20 MT/year from considering numerous scenarios. It appears that some benefit may be derived from advanced processes for separating fission products from molten salt waste, but the degree of improvement is limited. Waste form production is also considered but appears to be economically unfavorable. Direct disposal of salt into a salt basin type repository is found to be the most promising with respect to minimizing the impact of waste generation on the economic feasibility and sustainability of pyroprocessing.

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

Science.gov (United States)

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

2017-03-09

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

1991 Acceptance priority ranking

International Nuclear Information System (INIS)

1991-12-01

The Standard Contract for Disposal of Spent Nuclear Fuel and/or High- Level Radioactive Waste (10 CFR Part 961) that the Department of Energy (DOE) has executed with the owners and generators of civilian spent nuclear fuel requires annual publication of the Acceptance Priority Ranking (APR). The 1991 APR details the order in which DOE will allocate Federal waste acceptance capacity. As required by the Standard Contract, the ranking is based on the age of permanently discharged spent nuclear fuel (SNF), with the owners of the oldest SNF, on an industry-wide basis, given the highest priority. the 1991 APR will be the basis for the annual allocation of waste acceptance capacity to the Purchasers in the 1991 Annual Capacity Report (ACR), to be issued later this year. This document is based on SNF discharges as of December 31, 1990, and reflects Purchaser comments and corrections, as appropriate, to the draft APR issued on May 15, 1991

Optimization on Pretreatment Conditions of Seaweed Liquid Waste for Bio ethanol Production

International Nuclear Information System (INIS)

Nur Zatul-Iffah Zakaria; Dachyar Arbain; Mohd Noor Ahmad; Mohd Irfan Hatim Mohamed Dzahir

2015-01-01

Seaweed liquid waste (SLW) from a non-conventional seaweed (Gracilaria sp.) drying process where the seaweed is ruptured and filter-squeezed has been investigated. The liquid contains proteins and minerals which potentially pollute the environment if it is not been properly treated. For that reason, this paper deals with study on the feasibility of SLW utilization as a feedstock for bio ethanol production. The fermentation of bio ethanol production was carried out by Saccharomyces cerevisiae in which ethanol produced was measured by gas chromatography. In order to increase its fermentable sugar content, the SLW was treated with dilute acid. Center composite design of response surface methodology (RSM) had been used to optimize the sugar content by varying the parameters involved in the dilute acid pretreatment conditions. These are sulphuric acid concentration (M), temperature (degree Celsius) and seaweed waste concentration (g/ ml). It was obtained that the R 2 value reached 0.97 indicating that the model is acceptable. The three parameters showed p-value less than 0.05 suggesting their significance interactions. The optimization resulted 25 times improvement of reducing sugar concentration. The reducing sugar resulting from the optimized pretreatment was later used as fermentation medium to produce ethanol up to 123.197 mg/ l. (author)

Methane production from fermentation of winery waste

Energy Technology Data Exchange (ETDEWEB)

Lo, K V; Liao, P H

1986-01-01

A laboratory-scale reactor receiving a mixture of screened dairy manure and winery waste was studied at 35 degrees C and a hydraulic retention time of 4 days. The maximum methane production rate of 8.14 liter CH/sub 4//liter/day was achieved at a loading rate of 7.78 g VS/liter/day (VS = volatile solids). The corresponding methane yield was 1.048 liter CH/sub 4//g VS added. Using a mixture of winery wastes and screened dairy manure as the feed material to anaerobic reactor resulted in a significant increase in total methane production compared to that from screened dairy manure alone. The biodegradation efficiency increased with the addition of winery wastes to screened dairy manure. 18 references.

The waste minimization program at the Feed Materials Production Center

International Nuclear Information System (INIS)

Blasdel, J.E.; Crotzer, M.E.; Gardner, R.L.; Kato, T.R.; Spradlin, C.N.

1987-01-01

A waste minimization program is being implemented at the Feed Materials Production Center to reduce the generation of uranium-contaminated wastes and to comply with existing and forthcoming regulations. Procedures and plans are described which deal with process and non-process trash, contaminated wood and metals, used metal drums, and major process wastes such as contaminated magnesium fluoride and neutralized raffinate. Waste minimization techniques used include segregation, source reduction, volume reduction, material substitution and waste/product recycle. The importance of training, communication, and incentives is also covered. 5 refs., 11 figs

Product/Process (P/P) Models For The Defense Waste Processing Facility (DWPF): Model Ranges And Validation Ranges For Future Processing

Energy Technology Data Exchange (ETDEWEB)

Jantzen, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Edwards, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-09-25

Radioactive high level waste (HLW) at the Savannah River Site (SRS) has successfully been vitrified into borosilicate glass in the Defense Waste Processing Facility (DWPF) since 1996. Vitrification requires stringent product/process (P/P) constraints since the glass cannot be reworked once it is poured into ten foot tall by two foot diameter canisters. A unique “feed forward” statistical process control (SPC) was developed for this control rather than statistical quality control (SQC). In SPC, the feed composition to the DWPF melter is controlled prior to vitrification. In SQC, the glass product would be sampled after it is vitrified. Individual glass property-composition models form the basis for the “feed forward” SPC. The models transform constraints on the melt and glass properties into constraints on the feed composition going to the melter in order to guarantee, at the 95% confidence level, that the feed will be processable and that the durability of the resulting waste form will be acceptable to a geologic repository.

Electricity production from municipal solid waste in Brazil.

Science.gov (United States)

Nordi, Guilherme Henrique; Palacios-Bereche, Reynaldo; Gallego, Antonio Garrido; Nebra, Silvia Azucena

2017-07-01

Brazil has an increasing production of municipal solid waste that, allied to the current waste management system, makes the search for alternatives of energy recovery essential. Thus, this work aims to study the incineration of municipal solid waste and the electricity production through steam cycles evaluating the influence of municipal solid waste composition. Several scenarios were studied, in which it was assumed that some fractions of municipal solid waste were removed previously. The municipal solid waste generated in Santo André city, São Paulo State, Brazil, was adopted for this study. Simulation results showed that the removal of organic matter and inert components impacts advantageously on the cycle performance, improving their parameters in some cases; in addition, there is the possibility of reusing the separated fractions. The separation of some recyclables, as plastic material, showed disadvantages by the reduction in the electricity generation potential owing to the high calorific value of plastics. Despite the high energy content of them, there are other possible considerations on this subject, because some plastics have a better recovery potential by recycling.

Selection of a leaching test method for waste product conformity verification

Energy Technology Data Exchange (ETDEWEB)

Lopes, Isabel Sofia R.F.S.; Tello, Clédola Cássia O.; Haucz, Maria Judite A., E-mail: isabel.lopes@cdtn.br, E-mail: tellocc@cdtn.br, E-mail: hauczmj@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2017-07-01

A study on the waste acceptance criteria (WAC) for disposal in a near-surface repository is being implemented by CDTN / CNEN. The acceptance criteria are used to ensure the safety in the repository facility in order to protect the employees, the public and the environment from some possible harmful and dangerous effects of the ionizing radiation. A near-surface repository is intended to be built for disposal of the Brazilian low- and intermediate level wastes. Leaching was the criterion chosen to be studied in this research. It is extremely important for the safety assessment to evaluate the waste form in relation to the radionuclides release, to predict the repository performance in the long term. As in the Brazilian WAC the test to measure the radionuclides leaching is not defined yet, two leaching tests were selected to be performed, the ISO 6961 and the ASTM C1308. The results will be analyzed in order to verify their similarities and differences and also their advantages and disadvantages. Inactive tracers cesium and lead were used as tracers to follow the leaching in both procedures. (author)

Selection of a leaching test method for waste product conformity verification

International Nuclear Information System (INIS)

Lopes, Isabel Sofia R.F.S.; Tello, Clédola Cássia O.; Haucz, Maria Judite A.

2017-01-01

A study on the waste acceptance criteria (WAC) for disposal in a near-surface repository is being implemented by CDTN / CNEN. The acceptance criteria are used to ensure the safety in the repository facility in order to protect the employees, the public and the environment from some possible harmful and dangerous effects of the ionizing radiation. A near-surface repository is intended to be built for disposal of the Brazilian low- and intermediate level wastes. Leaching was the criterion chosen to be studied in this research. It is extremely important for the safety assessment to evaluate the waste form in relation to the radionuclides release, to predict the repository performance in the long term. As in the Brazilian WAC the test to measure the radionuclides leaching is not defined yet, two leaching tests were selected to be performed, the ISO 6961 and the ASTM C1308. The results will be analyzed in order to verify their similarities and differences and also their advantages and disadvantages. Inactive tracers cesium and lead were used as tracers to follow the leaching in both procedures. (author)

International technology exchange in support of the Defense Waste Processing Facility wasteform production

International Nuclear Information System (INIS)

Kitchen, B.G.

1989-01-01

The nearly completed Defense Waste Processing Facility (DWPF) is a Department of Energy (DOE) facility at the Savannah River Site that is designed to immobilize defense high level radioactive waste (HLW) by vitrification in borosilicate glass and containment in stainless steel canisters suitable for storage in the future DOE HLW repository. The DWPF is expected to start cold operation later this year (1990), and will be the first full scale vitrification facility operating in the United States, and the largest in the world. The DOE has been coordinating technology transfer and exchange on issues relating to HLW treatment and disposal through bi-lateral agreements with several nations. For the nearly fifteen years of the vitrification program at Savannah River Laboratory, over two hundred exchanges have been conducted with a dozen international agencies involving about five-hundred foreign national specialists. These international exchanges have been beneficial to the DOE's waste management efforts through confirmation of the choice of the waste form, enhanced understanding of melter operating phenomena, support for paths forward in political/regulatory arenas, confirmation of costs for waste form compliance programs, and establishing the need for enhancements of melter facility designs. This paper will compare designs and schedules of the international vitrification programs, and will discuss technical areas where the exchanges have provided data that have confirmed and aided US research and development efforts, impacted the design of the DWPF and guided the planning for regulatory interaction and product acceptance

Reevaluation Of Vitrified High-Level Waste Form Criteria For Potential Cost Savings At The Defense Waste Processing Facility

International Nuclear Information System (INIS)

Ray, J. W.; Marra, S. L.; Herman, C. C.

2013-01-01

At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a durable borosilicate glass since 1996. Currently the DWPF has poured over 3,500 canisters, all of which are compliant with the U. S. Department of Energy's (DOE) Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms (WAPS) and therefore ready to be shipped to a federal geologic repository for permanent disposal. Due to DOE petitioning to withdraw the Yucca Mountain License Application (LA) from the Nuclear Regulatory Commission (NRC) in 2010 and thus no clear disposal path for SRS canistered waste forms, there are opportunities for cost savings with future canister production at DWPF and other DOE producer sites by reevaluating high-level waste form requirements and compliance strategies and reducing/eliminating those that will not negatively impact the quality of the canistered waste form

Cements in radioactive waste management. Characterization requirements of cement products for acceptance and quality assurance purposes

International Nuclear Information System (INIS)

Rahman, A.A.; Glasser, F.P.

1987-01-01

Cementitious materials are used as immobilizing matrices for low (LLW) and medium-level wastes (MLW) and are also components of the construction materials in the secondary barriers and the repositories. This report has concerned itself with a critical assessment of the quality assurance aspects of the immobilization and disposal of MLW and LLW cemented wastes. This report has collated the existing knowledge of the use and potential of cementitious materials in radioactive waste immobilization and highlighted the physico-chemical parameters. Subject areas include an assessment of immobilization objectives and cement as a durable material, waste stream and matrix characterization, quality assurance concepts, nature of cement-based systems, chemistry and modelling of cement hydration, role and effect of blending agents, radwaste-cement interaction, assessment of durability, degradative and radiolytic processes in cements and the behaviour of cement-based matrices and their near-field interactions with the environment and the repository conditions

Production of proteases from organic wastes by solid-state fermentation: downstream and zero waste strategies.

Science.gov (United States)

Marín, Maria; Artola, Adriana; Sánchez, Antoni

2018-04-01

Production of enzymes through solid-state fermentation (SSF) of agro-industrial wastes reports high productivity with low investment. The extraction of the final product from the solid waste and solid disposal represent the main cost of the process. In this work, the complete downstream processes of SSF of two industrial residues for the production of proteases, soy fibre (SF) and a mixture of hair and sludge (HS), were studied in terms of activity recovery, using different extraction parameters (extracting solvent, ratio solid: solvent and extraction mode). Activity after lyophilisation was tested. Solid waste valorisation after extraction was studied using respiration techniques and biogas production tests, as part of a zero waste strategy. Results showed a maximum extraction yield of 91% for SF and 121% for HS, both in agitated mode and distilled water as extraction agent. An average activity recovery of 95 ± 6 and 94 ± 6% for SF and HS, respectively, was obtained after lyophilisation and redissolution. To reduce the cost of extraction, a ratio 1:3 w : v solid-solvent in static mode is advised for SF, and 1:2 w : v extraction ratio in agitated mode for HS, both with distilled water as extracting agent. Both composting and anaerobic digestion are suitable techniques for valorisation of the waste material.

Enhanced Bio-Ethanol Production from Industrial Potato Waste by Statistical Medium Optimization

OpenAIRE

Izmirlioglu, Gulten; Demirci, Ali

2015-01-01

Industrial wastes are of great interest as a substrate in production of value-added products to reduce cost, while managing the waste economically and environmentally. Bio-ethanol production from industrial wastes has gained attention because of its abundance, availability, and rich carbon and nitrogen content. In this study, industrial potato waste was used as a carbon source and a medium was optimized for ethanol production by using statistical designs. The effect of various medium componen...

Bacterial Cellulose Production from Industrial Waste and by-Product Streams

Directory of Open Access Journals (Sweden)

Erminda Tsouko

2015-07-01

Full Text Available The utilization of fermentation media derived from waste and by-product streams from biodiesel and confectionery industries could lead to highly efficient production of bacterial cellulose. Batch fermentations with the bacterial strain Komagataeibacter sucrofermentans DSM (Deutsche Sammlung von Mikroorganismen 15973 were initially carried out in synthetic media using commercial sugars and crude glycerol. The highest bacterial cellulose concentration was achieved when crude glycerol (3.2 g/L and commercial sucrose (4.9 g/L were used. The combination of crude glycerol and sunflower meal hydrolysates as the sole fermentation media resulted in bacterial cellulose production of 13.3 g/L. Similar results (13 g/L were obtained when flour-rich hydrolysates produced from confectionery industry waste streams were used. The properties of bacterial celluloses developed when different fermentation media were used showed water holding capacities of 102–138 g·water/g·dry bacterial cellulose, viscosities of 4.7–9.3 dL/g, degree of polymerization of 1889.1–2672.8, stress at break of 72.3–139.5 MPa and Young’s modulus of 0.97–1.64 GPa. This study demonstrated that by-product streams from the biodiesel industry and waste streams from confectionery industries could be used as the sole sources of nutrients for the production of bacterial cellulose with similar properties as those produced with commercial sources of nutrients.

Prevention and Minimization of Waste Production

International Nuclear Information System (INIS)

Noynaert, L.; Bruggeman, A.; Rahier, A.

1998-01-01

The general objectives of SCK-CEN's programme on the prevention and minimization of waste production are to contribute to reducing volumes and cost of radioactive waste. It also aims tro provide reliable data and models to the design engineers with a view to determining the final plant characteristics. In the long term, these objectives will be extended to other nuclear applications. Progress and achievements in 1997 are summarised

THE ACCEPTANCE OF HEALTH RELATED INNOVATIONS IN TRADITIONAL MEAT PRODUCTS BY CROATIAN CONSUMERS

Directory of Open Access Journals (Sweden)

Danijel Karolyi

2015-09-01

Full Text Available The aim of this study was to examine Croatian consumers’ acceptance of health related innovations in traditional meat products. A face-to-face survey was conducted with a sample of 151 visitors of a specialized fair of traditional food products in Zagreb in 2013. The respondents were asked to indicate their attitudes on a fivepoint scale, where 1 meant rejection or no impact and 5 meant full acceptance or high impact. Results (mean±SD showed the highest level of acceptance for innovations related to better control of smoking conditions (3.3± 1.14 and reduction of salt content (3.1±1.15, followed by reduced fat content (3.0±1.14 and controlled fermentation (2.9±1.12. The perceived negative impact of innovations on traditional character of meat products was highest for fat (3.4±0.99 and salt (3.4±1.03 reduction and lowest for controlled fermentation (3.2±1.04 and smoking conditions (3.2±1.05. With regards to respondents’ socio-demographic features a nonparametric test statistic (Mann-Whitney U revealed a higher acceptance of fat reduction and higher willingness to increase a consumption of healthier traditional meat products among females, while age, education level and income had no influence on the investigated parameters. In addition, some health related innovations; e.g. fat reduction and controlled fermentation were generally less acceptable among respondents with a high consumption frequency of traditional meat products. The results of this preliminary study indicated controlled smoking conditions as the best accepted health related innovation by Croatian consumers with the least negative impact on perceived traditional character of product. In general terms, women were more likely to accept some of the investigated innovations and consequently to increase their consumption of innovate products. However, the most regular consumers of traditional meat products were less open towards innovations which may pose a challenge to

Systems evolution of waste and by-product management and bioenergy production

Energy Technology Data Exchange (ETDEWEB)

Okkonen, L.

2009-07-01

Evolutionary economic geography provides an inspiring extension to geographical systems analysis. The objective of this dissertation is to apply the systems approach and theory as an integrative framework of sustainable development, and as a capable analytical tool in the analysis of evolutionary resource management and energy production systems in their geographical contexts. The systems investigated are waste and by-product management and bioenergy production systems located in Finland and Scotland. Industrial ecosystem (IE) indicators are constructed for the analysis of waste and by-product management. They present both direct and indirect environmental, economic and social impacts of local waste management operations. The indicators are further applied in scenarios that dynamise the evolution of systems material and energy flows towards the balanced environmental, economic and social development, i.e. the vision of the industrial ecology. The results indicate that the energy use of waste derived fuels in regional cooperation has much potential in the development towards the optimal roundput model of industrial ecosystem. The business opportunities based on local woodfuels are investigated in the context of Scottish forestry policy. The evolution of institutional environments and arrangements of forest management in the Scottish Highlands enables a new type of rural entrepreneurship. The case study of Finnish heat entrepreneurship constructs a heat energy business model, including both the business architecture for product/service flows and the earning logics. Finally, a synthesis of the evolution of natural resource management systems is presented. The evolution process has many geographical contingent conditions, such as resources, technologies, institutions and organisations. Together with general socio-economic mechanisms, they affect the actors in spatial economic processes and interactions. Realisations of the system evolution are structures of economies

Consumers’ acceptance and preferences for nutrition-modified and functional dairy products

NARCIS (Netherlands)

Bimbo, Francesco; Bonanno, Alessandro; Nocella, Giuseppe; Viscecchia, Rosaria; Nardone, Gianluca; Devitiis, De Biagia; Carlucci, Domenico

2017-01-01

This systematic literature review collects and summarizes research on consumer acceptance and preferences for nutrition-modified and functional dairy products, to reconcile, and expand upon, the findings of previous studies. We find that female consumers show high acceptance for some functional

DWPF waste form compliance plan (Draft Revision)

International Nuclear Information System (INIS)

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

1991-01-01

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

The influence of slaughterhouse waste on fermentative H{sub 2} production from food waste: Preliminary results

Energy Technology Data Exchange (ETDEWEB)

Boni, Maria Rosaria; Sbaffoni, Silvia; Tuccinardi, Letizia, E-mail: letizia.tuccinardi@uniroma1.it

2013-06-15

Highlights: • Co-digestion process finalized to bio-H{sub 2} production was tested in batch tests. • Slaughterhouse waste (SHW) and food waste (FW) were co-digested in different proportions. • The presence of SHW affected the H{sub 2} production from FW. • When SHW ranging between 50% and 70% the H{sub 2} production is improved. • SHW percentages above 70%, led to a depletion in H{sub 2} production. - Abstract: The aim of this study was to evaluate the influence of slaughterhouse waste (SHW; essentially the skin, fats, and meat waste of pork, poultry, and beef) in a fermentative co-digestion process for H{sub 2} production from pre-selected organic waste taken from a refectory (food waste [FW]). Batch tests under mesophilic conditions were conducted in stirred reactors filled with different proportions of FW and SHW. The addition of 60% and 70% SHW to a mixture of SHW and FW improved H{sub 2} production compared to that in FW only, reaching H{sub 2}-production yields of 145 and 109 ml gVS{sub 0}{sup -1}, respectively, which are 1.5–2 times higher than that obtained with FW alone. Although the SHW ensured a more stable fermentative process due to its high buffering capacity, a depletion of H{sub 2} production occurred when SHW fraction was higher than 70%. Above this percentage, the formation of foam and aggregated material created non-homogenous conditions of digestion. Additionally, the increasing amount of SHW in the reactors may lead to an accumulation of long chain fatty acids (LCFAs), which are potentially toxic for anaerobic microorganisms and may inhibit the normal evolution of the fermentative process.

Technical considerations associated with spent fuel acceptance. Final report

International Nuclear Information System (INIS)

Supko, E.M.

1996-06-01

This study was initiated by the Electric Power Research Institute (EPRI) to identify technical considerations associated with spent fuel acceptance and implementation of a waste management system that includes the use of transportable storage systems, and to serve as an opening dialogue among Standard Contract Holders and the department of Energy's Office of Civilian Radioactive Waste management (OCRWM) prior to the development of waste acceptance criteria or issuance of a Notice of Proposed Rulemaking by OCRWM to amend the Standard Contract. The original purpose of the Notice of Proposed Rulemaking was to address changes to the Standard Contract to implement a multi-purpose canister based system and to address other issues that were not adequately addressed in the standard contract. Even if DOE does not develop a multi-purpose canister based system for waste acceptance, it will still be necessary to develop waste acceptance criteria in order to accept spent fuel in transportable storage systems that are being deployed for at-reactor storage. In this study, technical issues associated with spent fuel acceptance will be defined and potential options and alternatives for resolution of technical considerations will be explored

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

International Nuclear Information System (INIS)

2010-01-01

The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site

Energy Technology Data Exchange (ETDEWEB)

NSTec Environmental Programs

2010-10-04

The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is

Long-term properties of bituminized waste products

International Nuclear Information System (INIS)

Snellman, M.; Valkiainen, M.

1985-10-01

This study is a survey of the factors of importance for the long term behaviour of bituminized ion exchange resins. Phenomena occurring in bituminized waste products affected by the treatment, storage and disposal are identified. Test methods have been developed for characterizing product properties, which are important for the long-term behaviour. The long-term properties of bituminized ion-exchange resins are studied in a repository environment with access of water equilibrated with concrete. In these circumstances the most important properties are related to the interactions of bituminized waste with the surrounding barriers. The most important phenomena are water uptake due to rehydration of the resins and subsequent swelling of the product

Long-term properties of bituminized waste products

International Nuclear Information System (INIS)

Snellman, M.; Valkiainen, M.

1985-10-01

This study is a survey of the factors of importance for long term behaviour of bituminized ion exchange resins. Phenomena occurring in bituminized waste products affected by the treatment, storage and disposal are identified. Test methods have been developed for characterizing product properties, which are important for the long-term behaviour. The long-term properties of bituminized ion-exchange resins are studied in a repository environment with access of water equilibrated with concrete. In these circumstances the most important properties are ralated to the interactions of bituminized waste with the surrounding barriers. The most important phenomena are water uptake due to rehydration of the resins and subsequent swelling of the product. (author)

Transesterification of Waste Cooking Sunflower Oil by Porcine Pancreas Lipase Using Response Surface Methodology for Biodiesel Production

Directory of Open Access Journals (Sweden)

Soraya Ebrahimi

2017-09-01

Full Text Available Background and Objective: Biodiesel production from recycled vegetable oils is considered as an economically acceptable alternative for fossil fuels in the recent years. In this work, porcine pancreas lipase as an active catalyst in transesterification reaction of waste cooking sunflower oil with methanol for biodiesel production was used.Material and Methods: In order to define optimum process parameters and predict the best results, response surface methodology and the central composite design was performed. The effects of methanol to oil molar ratio, lipase concentration and reaction temperature on transesterification were investigated. Biodiesel production was carried out in 25 ml shake flasks at 180 rpm for 72 h.Results and Conclusion: Under optimal conditions, the biodiesel yield was 75% which was nearly consistent with the predicted yield of 76%. At optimal conditions the molar ratio of methanol to oil, reaction temperature, and lipase percent were determined as 3:1, 44°C and 4.4%, respectively. Due to relatively high obtained yield, biodiesel production from waste cooking sunflower oil has provided a sound environmental and commercial process.Conflict of interest: The authors declare no conflict of interest.

Assessment of national systems for obtaining local siting acceptance of nuclear waste management facilities (October 1, 1985). Volume I. Political structure and formal system for obtaining approvals for siting waste management facilities

International Nuclear Information System (INIS)

Paige, H.W.; Numark, N.J.

1985-01-01

This report is the fourth in a series of periodic surveys of approaches and progress in other countries in dealing with the problems of obtaining local acceptance for siting of waste management facilities. This volume contains the following sections: Nation's political/industrial structure for obtaining waste management siting decisions; and Nation's formal legal procedure for obtaining necessary approvals for siting nuclear waste management facilities. Two of the countries visited, Finland and Sweden, have had major changes in the past two years in their formal/legal procedures for obtaining waste management siting decisions. (LM)

The low-level waste handling challenge at the Feed Materials Production Center

International Nuclear Information System (INIS)

Harmon, J.E.; Diehl, D.E.; Gardner, R.L.

1988-02-01

The management of low-level wastes from the production of depleted uranium at the Feed Materials Production Center presents an enormous challenge. The recovery of uranium from materials contaminated with depleted uranium is usually not economical. As a result, large volumes of wastes are generated. The Westinghouse Materials Company of Ohio has established an aggressive waste management program. Simple solutions have been applied to problems in the areas of waste handling and waste minimization. The success of this program has been demonstrated by the reduction of low-level waste inventory at the Feed Materials Production Center. 8 refs., 4 figs

The low-level waste handling challenge at the Feed Materials Production Center

International Nuclear Information System (INIS)

Harmon, J.E.; Diehl, D.E.; Gardner, R.L.

1988-01-01

The management of low-level wastes from the production of depleted uranium at the Feed Materials Production Center presents an enormous challenge. The recovery of uranium from materials contaminated with depleted uranium is usually not economical. As a result, large volumes of wastes are generated. The Westinghouse Materials Company of Ohio has established an aggressive waste management program. Simple solutions have been applied to problems in the areas of waste handling and waste minimization. The success of this program has been demonstrated by the reduction of low-level waste inventory at the Feed Materials Production Center

Hanford immobilized LAW product acceptance: Initial Tanks Focus Area testing data package

Energy Technology Data Exchange (ETDEWEB)

JD Vienna; A Jiricka; BP McGrail; BM Jorgensen; DE Smith; BR Allen; JC Marra; DK Peeler; KG Brown; IA Reamer; WL Ebert

2000-03-08

The Hanford Site's mission has been to produce nuclear materials for the US Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during plutonium production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The total volume of LAW requiring immobilization will include the LAW separated from the tank waste, as well as new wastes generated by the retrieval, pretreatment, and immobilization processes. Per the Tri-Party Agreement (1994), both the LAW and HLW will be vitrified. It has been estimated that vitrification of the LAW waste will result in over 500,000 metric tons or 200,000 m{sup 3} of immobilized LAW (ILAW) glass. The ILAW glass is to be disposed of onsite in a near-surface burial facility. It must be demonstrated that the disposal system will adequately retain the radionuclides and prevent contamination of the surrounding environment. This report describes a study of the impacts of systematic glass-composition variation on the responses from accelerated laboratory corrosion tests of representative LAW glasses. A combination of two tests, the product consistency test and vapor-hydration test, is being used to give indictations of the relative rate at which a glass could be expected to corrode in the burial scenario.

Hanford immobilized LAW product acceptance: Initial Tanks Focus Area testing data package

International Nuclear Information System (INIS)

JD Vienna; A Jiricka; BP McGrail; BM Jorgensen; DE Smith; BR Allen; JC Marra; DK Peeler; KG Brown; IA Reamer; WL Ebert

2000-01-01

The Hanford Site's mission has been to produce nuclear materials for the US Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during plutonium production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The total volume of LAW requiring immobilization will include the LAW separated from the tank waste, as well as new wastes generated by the retrieval, pretreatment, and immobilization processes. Per the Tri-Party Agreement (1994), both the LAW and HLW will be vitrified. It has been estimated that vitrification of the LAW waste will result in over 500,000 metric tons or 200,000 m 3 of immobilized LAW (ILAW) glass. The ILAW glass is to be disposed of onsite in a near-surface burial facility. It must be demonstrated that the disposal system will adequately retain the radionuclides and prevent contamination of the surrounding environment. This report describes a study of the impacts of systematic glass-composition variation on the responses from accelerated laboratory corrosion tests of representative LAW glasses. A combination of two tests, the product consistency test and vapor-hydration test, is being used to give indictations of the relative rate at which a glass could be expected to corrode in the burial scenario

Derivation of quantitative acceptance criteria for disposal of radioactive waste to near surface facilities: Development and implementation of an approach for the post-closure phase

International Nuclear Information System (INIS)

Torres, C.

2000-01-01

The International Atomic Energy Agency has established a project to develop and illustrate, through practical examples, an approach that allows the derivation of quantitative waste acceptance criteria for near surface disposal of radioactive waste. The first phase focussed on the derivation of example post-closure safety waste acceptance criteria through the use of a safety assessment approach that allows for the derivation of values in a clear and well documented manner. The approach consists of five steps: the specification of the assessment context; the description of the disposal system; the development and justification of scenarios; the formulation and implementation of models; and the calculation and derivation of example values. The approach has been successfully used to derive activity values for the disposal of radioactive waste to illustrative near surface facilities. (author)

Plutonium and surrogate fission products in a composite ceramic waste form

International Nuclear Information System (INIS)

Esh, D. W.; Frank, S. M.; Goff, K. M.; Johnson, S. G.; Moschetti, T. L.; O'Holleran, T.

1999-01-01

Argonne National Laboratory is developing a ceramic waste form to immobilize salt containing fission products and transuranic elements. Preliminary results have been presented for ceramic waste forms containing surrogate fission products such as cesium and the lanthanides. In this work results from scanning electron microscopy/energy dispersive spectroscopy and x-ray diffraction are presented in greater detail for ceramic waste forms containing surrogate fission products. Additionally, results for waste forms containing plutonium and surrogate fission products are presented. Most of the surrogate fission products appear to be silicates or aluminosilicates whereas the plutonium is usually found in an oxide form. There is also evidence for the presence of plutonium within the sodalite phase although the chemical speciation of the plutonium is not known

Biodiesel production using oil from fish canning industry wastes

International Nuclear Information System (INIS)

Costa, J.F.; Almeida, M.F.; Alvim-Ferraz, M.C.M.; Dias, J.M.

2013-01-01

Highlights: • A process was established to produce biodiesel from fish canning industry wastes. • Biodiesel production was enabled by an acid esterification pre-treatment. • Optimization studies showed that the best catalyst concentration was 1 wt.% H 2 SO 4 . • There was no advantage when a two-step alkali transesterification was employed. • Waste oil from olive oil bagasse could be used to improve fuel quality. - Abstract: The present study evaluated biodiesel production using oil extracted from fish canning industry wastes, focusing on pre-treatment and reaction conditions. Experimental planning was conducted to evaluate the influence of acid catalyst concentration (1–3 wt.% H 2 SO 4 ) in the esterification pre-treatment and the amount of methanolic solution (60–90 vol.%) used at the beginning of the further two-step alkali transesterification reaction. The use of a raw-material mixture, including waste oil obtained from olive oil bagasse, was also studied. The results from experimental planning showed that catalyst concentration mostly influenced product yield and quality, the best conditions being 1 wt.% catalyst and 60 vol.% of methanolic solution, to obtain a product yield of 73.9 wt.% and a product purity of 75.5 wt.%. Results from a one-step reaction under the selected conditions showed no advantage of performing a two-step alkali process. Although under the best conditions several of the biodiesel quality parameters were in agreement with standard specifications, a great variation was found in the biodiesel acid value, and oxidation stability and methyl ester content did not comply with biodiesel quality standards. Aiming to improve fuel quality, a mixture containing 80% waste olive oil and 20% of waste fish oil was evaluated. Using such mixture, biodiesel purity increased around 15%, being close to the standard requirements (96.5 wt.%), and the oxidation stability was in agreement with the biodiesel quality standard values (⩾6 h), which

The use of waste cellulose in production of white mushroom substrate

Directory of Open Access Journals (Sweden)

Ivan Kameník

2011-01-01

Full Text Available The employment of industrial wastes in agricultural production is one of the possible ways of waste management. Composting of organic waste can cut the cost of transport and disposal of these wastes while obtaining cheep resource materials for the production of composts. Apart from composting or using wastes in the biogas plants, there is yet another possibility of using local organic waste and it is its employment as a component of substrate (compost for the white mushroom growing. This study deals with the use of waste cellulose in the production of white mushroom substrate. The aim of this study is to evaluate the impact of cellulose content in the substrate on the level of mushroom crop when the mushrooms are grown in the form of compacted substrate designed for small growers. The greatest emphasis is placed on matters of efficient yield of the mushrooms and which are considered to be indispensable for achieving production results over a longer period. This means first and foremost the growing methods and growing environment in the small growing plant. This way the growers could overwhelm the very complicated calculation before the compost preparing. Thanks this way the producers can obtain the utmost probability of the stable crops in the package form of the substrate. The research shows the potential for using of the waste material and fostering the environment friendly food production.

Waste management from pulp and paper production in the European Union

International Nuclear Information System (INIS)

Monte, M.C.; Fuente, E.; Blanco, A.; Negro, C.

2009-01-01

Eleven million tonnes of waste are produced yearly by the European pulp and paper industry, of which 70% originates from the production of deinked recycled paper. Wastes are very diverse in composition and consist of rejects, different types of sludges and ashes in mills having on-site incineration treatment. The production of pulp and paper from virgin pulp generates less waste but the waste has similar properties to waste from the production of deinked pulp, although with less inorganics. Due to legislation and increased taxes, landfills are quickly being eliminated as a final destination for wastes in Europe, and incineration with energy recovery is becoming the main waste recovery method. Other options such as pyrolysis, gasification, land spreading, composting and reuse as building material are being applied, although research is still needed for optimization of the processes. Due to the large volumes of waste generated, the high moisture content of the waste and the changing waste composition as a result of process conditions, recovery methods are usually expensive and their environmental impact is still uncertain. For this reason, it is necessary to continue research on different applications of wastes, while taking into account the environmental and economic factors of these waste treatments

Coffee husk waste for fermentation production of mosquitocidal bacteria.

Science.gov (United States)

Poopathi, Subbiah; Abidha, S

2011-12-01

Coffee husk waste (CHW) discarded as bio-organic waste, from coffee industries, is rich in carbohydrates. The current study emphasizes the management of solid waste from agro-industrial residues for the production of biopesticides (Bacillus sphaericus, and B. thuringiensis subsp. israelensis), to control disease transmitting mosquito vectors. An experimental culture medium was prepared by extracting the filtrates from coffee husk. A conventional culture medium (NYSM) also was prepared. The studies revealed that the quantity of mosquitocidal toxins produced from CHW is at par with NYSM. The bacteria produced in these media, were bioassayed against mosquito vectors (Culex quinquefasciatus, Anopheles stephensi, and Aedes aegypti) and it was found that the toxic effect was statistically comparable. Cost-effective analysis have revealed that, production of biopesticides from CHW is highly economical. Therefore, the utilization of CHW provides dual benefits of effective utilization of environmental waste and efficient production of mosquitocidal toxins.

Potential useful products from solid wastes.

Science.gov (United States)

Golueke, C G; Diaz, L F

1991-10-01

Wastes have been aptly defined as "items, i.e. resources, that have been discarded because their possessors no longer have an apparent use for them". Accordingly, "wastes" have a significance only in relation to the items and those who have discarded them. The discarded items now are resources awaiting reclamation. Reclamation usually involves either salvage or conversion--or in modern terminology, "reuse" or "recycling". Reclamation for reuse consists in refurbishing or other upgrading without significantly altering original form and composition. Examples of wastes amenable to reuse are containers (bottles, etc.), cartons and repairable tires. With "recycling" (i.e. conservation), the discarded items are processed such that they become raw material, i.e. resources in the manufacture of "new" products. The variety of processes is wide, ranging from simply physical (grinding) through thermal (melting, gasification, combustion), to biological (composting, biogasification, hydrolysis, microbial protein production). In the paper, reuse and recycling (conversion) are evaluated in terms of advantages and disadvantages (limitations) and their respective technologies are described and discussed in detail.

PEA PEEL WASTE: A LIGNOCELLULOSIC WASTE AND ITS UTILITY IN CELLULASE PRODUCTION BY Trichoderma reesei UNDER SOLID STATE CULTIVATION

Directory of Open Access Journals (Sweden)

Nitin Verma

2011-03-01

Full Text Available A wide variety of waste bioresources are available on our planet for conversion into bioproducts. In the biological systems, microorganisms are used to utilize waste as an energy source for the synthesis of valuable products such as biomass proteins and enzymes. The large quantities of byproducts generated during the processing of plant food involve an economic and environmental problem due to their high volumes and elimination costs. After isolation of the main constituent, there are abundant remains which represent an inexpensive material that has been undervalued until now. Pea peel waste is one of the undervalued, unused sources of energy that can serve as a potential source for cellulase production. Batch experiments have been performed, using pea peel waste as a carbon source for cellulase production under solid state cultivation by Trichoderma reesei. It was observed that 30 oC temperature and pH 5.0 are the most favorable conditions for cellulase production by T. reesei. FPase activity significantly increases by incorporation of whey as well as wheat starch hydrolysate in the basal salt media used in the production study. The present study describes the utility of pea peel waste, whey as well as wheat starch hydrolysate in cellulase production by T. reesei. The utilization of economically cheap, pea peel waste for cellulase production could be a novel, cost effective, and valuable approach in cellulase production as well as in solid waste management.

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

Structural acceptance criteria for the evaulation of existing double-shell waste storage tanks located at the Hanford site, Richland, Washington

International Nuclear Information System (INIS)

Julyk, L.J.; Day, A.D.; Dyrness, A.D.; Moore, C.J.; Peterson, W.S.; Scott, M.A.; Shrivastava, H.P.; Sholman, J.S.; Watts, T.N.

1995-09-01

The structural acceptance criteria contained herein for the evaluation of existing underground double-shell waste storage tanks located at the Hanford Site is part of the Life Management/Aging Management Program of the Tank Waste Remediation System. The purpose of the overall life management program is to ensure that confinement of the waste is maintained over the required service life of the tanks. Characterization of the present condition of the tanks, understanding and characterization of potential degradation mechanisms, and development of tank structural acceptance criteria based on previous service and projected use are prerequisites to assessing tank integrity, to projecting the length of tank service, and to developing and applying prudent fixes or repairs. The criteria provided herein summarize the requirements for the analysis and structural qualification of the existing double-shell tanks for continued operation. Code reconciliation issues and material degradation under aging conditions are addressed. Although the criteria were developed for double-shell tanks, many of the provisions are equally applicable to single-shell tanks. However, the criteria do not apply to the evaluation of tank appurtenances and buried piping

Mapping ENM from consumer products in solid waste flows in Denmark

DEFF Research Database (Denmark)

Heggelund, Laura Roverskov; Boldrin, Alessio; Hansen, Steffen Foss

To address the challenges regarding management of waste from ENM-enabled consumer products, we mapped the flow of these products available online in Denmark and the EU. To do this, we used the Nanodatabase (www.nanodb.dk). A representative sample of products from the database was analyzed......, and placed into suitable waste material fractions. Subsequently, the distribution of ENM in the individual waste fractions, by number of products, was found. Overall, the results showed that nanosilver was present in seven of the eight identified waste material fractions, whereas other ENMs (e.g. CNTs...... and silicon) were only present in one or two fractions. Furthermore, the waste material fraction "dirty plastic" was the most diversified, containing five different ENMs. To our knowledge this type of analysis has not previously been performed, and the results hold promise for gaining a better understanding...

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

Science.gov (United States)

Mehani, Insaf; Bouchekima, Bachir

2018-05-01

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

Production and properties of solidified high-level waste

International Nuclear Information System (INIS)

Brodersen, K.

1980-08-01

Available information on production and properties of solidified high-level waste are presented. The review includes literature up to the end of 1979. The feasibility of production of various types of solidified high-level wast is investigated. The main emphasis is on borosilicate glass but other options are also mentioned. The expected long-term behaviour of the materials are discussed on the basis of available results from laboratory experiments. Examples of the use of the information in safety analysis of disposal in salt formations are given. The work has been made on behalf of the Danish utilities investigation of the possibilities of disposal of high-level waste in salt domes in Jutland. (author)

Potential of fecal waste for the production of biomethane, bioethanol and biodiesel.

Science.gov (United States)

Gomaa, Mohamed A; Abed, Raeid M M

2017-07-10

Fecal waste is an environmental burden that requires proper disposal, which ultimately becomes also an economic burden. Because fecal waste is nutrient-rich and contains a diverse methanogenic community, it has been utilized to produce biomethane via anaerobic digestion. Carbohydrates and lipids in fecal waste could reach up to 50% of the dry weight, which also suggests a potential as a feedstock for bioethanol and biodiesel production. We measured biomethane production from fecal waste of cows, chickens, goats and humans and compared the microbial community composition before and after anaerobic digestion. We also compared the fecal waste for cellulase production, saccharification and fermentation to produce bioethanol and for lipid content and fatty acid profiles to produce biodiesel. All fecal waste produced biomethane, with the highest yield of 433.4±77.1ml CH 4 /g VS from cow fecal waste. Production of bioethanol was achieved from all samples, with chicken fecal waste yielding as high as 1.6±0.25g/l. Sludge samples exhibited the highest extractable portion of lipids (20.9±0.08wt%) and conversion to fatty acid methyl esters (11.94wt%). Utilization of fecal waste for the production of biofuels is environmentally and economically beneficial. Copyright © 2017 Elsevier B.V. All rights reserved.

Thermal conversion of municipal solid waste via hydrothermal carbonization: comparison of carbonization products to products from current waste management techniques.

Science.gov (United States)

Lu, Xiaowei; Jordan, Beth; Berge, Nicole D

2012-07-01

Hydrothermal carbonization (HTC) is a novel thermal conversion process that may be a viable means for managing solid waste streams while minimizing greenhouse gas production and producing residual material with intrinsic value. HTC is a wet, relatively low temperature (180-350 °C) thermal conversion process that has been shown to convert biomass to a carbonaceous residue referred to as hydrochar. Results from batch experiments indicate HTC of representative waste materials is feasible, and results in the majority of carbon (45-75% of the initially present carbon) remaining within the hydrochar. Gas production during the batch experiments suggests that longer reaction periods may be desirable to maximize the production of energy-favorable products. If using the hydrochar for applications in which the carbon will remain stored, results suggest that the gaseous products from HTC result in fewer g CO(2)-equivalent emissions than the gases associated with landfilling, composting, and incineration. When considering the use of hydrochar as a solid fuel, more energy can be derived from the hydrochar than from the gases resulting from waste degradation during landfilling and anaerobic digestion, and from incineration of food waste. Carbon emissions resulting from the use of the hydrochar as a fuel source are smaller than those associated with incineration, suggesting HTC may serve as an environmentally beneficial alternative to incineration. The type and extent of environmental benefits derived from HTC will be dependent on hydrochar use/the purpose for HTC (e.g., energy generation or carbon storage). Copyright © 2012 Elsevier Ltd. All rights reserved.

Management of radioactive waste from 99Mo production by nuclear fission

International Nuclear Information System (INIS)

Rego, Maria Eugenia de Melo

2013-01-01

Brazil intends to build a facility for the 99 Mo production through 235 U fission, once this radioisotope is largely used in nuclear medicine. This study aimed at estimating the physical, chemical and radiological characteristics of radioactive waste expected to be generated in that facility, and to provide theoretical subsides that can be used on the definition of a proper waste management system. Two production scenarios were established and the radioisotope inventories of the wastes were calculated by Scale®. From the chemical processing of the uranium targets the wastes were characterized on their chemical and radiological features. MicroShield® was used to determine the activity concentrations up to three months of 99 Mo production. In addition, this work presents dose rate calculation for several sizes of shielding and different amount of wastes, collected in a proper package for in-site transportation. Radionuclides responsible for higher doses were identified in order to facilitate choosing the most appropriate method for managing the wastes after their chemical separation and before their storage. These results are part of what is expected on radioactive wastes at a 99 Mo production facility and might help on the development of the waste management planning for that facility. (author)

Verifying generator waste certification: NTS waste characterization QA requirements

International Nuclear Information System (INIS)

Williams, R.E.; Brich, R.F.

1988-01-01

Waste management activities managed by the US Department of Energy (DOE) at the Nevada Test Site (NTS) include the disposal of low-level wastes (LLW) and mixed waste (MW), waste which is both radioactive and hazardous. A majority of the packaged LLW is received from offsite DOE generators. Interim status for receipt of MW at the NTS Area 5 Radioactive Waste Management Site (RWMS) was received from the state of Nevada in 1987. The RWMS Mixed Waste Management Facility (MWMF) is expected to be operational in 1988 for approved DOE MW generators. The Nevada Test Site Defense Waste Acceptance Criteria and Certification Requirements (NVO-185, Revision 5) delineates waste acceptance criteria for waste disposal at the NTS. Regulation of the hazardous component of mixed waste requires the implementation of US Environmental Protection Agency (EPA) requirements pursuant to the Resource Conservation and Recovery Act (RCRA). Waste generators must implement a waste certification program to provide assurance that the disposal site waste acceptance criteria are met. The DOE/Nevada Operations Office (NV) developed guidance for generator waste certification program plans. Periodic technical audits are conducted by DOE/NV to assess performance of the waste certification programs. The audit scope is patterned from the waste certification program plan guidance as it integrates and provides a common format for the applicable criteria. The criteria focus on items and activities critical to processing, characterizing, packaging, certifying, and shipping waste

Identification and understanding the factors affecting the public and political acceptance of long term storage of spent fuel and high-level radioactive wastes

International Nuclear Information System (INIS)

Gorea, Valica

2006-01-01

In the end of 2004, according to the information available to the IAEA, there were 440 nuclear reactors operating worldwide, with a total net capacity of 366.3 GW(e), 6 of them being connected to the grid in 2004 ( 2 in Ukraine, one each in China, Japan and the Russian Federation and a reconnection in Canada) by comparison with 2 connections and 2 re-connections in 2003. Also, in the end of 2004, 26 nuclear power plants were under construction with a total net capacity of 20.8 GW(e). The conclusion accepted by common consent is that the nuclear power is still in progress and represents one of the options for power security on long and middle term. If we refer to the nuclear fusion which will produce commercial electric power, over 30 - 40 years, in practically unlimited quantities, the above underlining becomes even more evident. Fortunately, besides the beneficent characteristics, such as: clean, stable as engendering and price, has also a negative characteristic, which generally breathes fear into the people: radioactive waste. A classification of the radioactive waste is not the target of this presentation. I just want to point that a nuclear power plant produces during the time spent fuel - long life high radioactive, generating heat. Another high radioactive waste have similar characteristics (HLW = High Level Waste) for which reason these two categories of wastes are treated together. The spent fuel and the High Level Waste are interim stored for cooling, for around 50 years, afterwards it is transferred to the final repository where it will be kept for hundreds of years, in the case of an open fuel cycle and this is also the case of Cernavoda NPP. Taking into consideration that the Cernavoda Unit 1 reaches the age of 10 years of commercial running during December 2006, it results that the issue of the final disposal is not such urgent as it looks. The objectives of long term management of radioactive waste are public health and protection of the environment

A review of literature relevant to gas production in radioactive waste

International Nuclear Information System (INIS)

Norris, G.H.

1987-11-01

A review of relevant recent papers on gas generation in low-level wastes and intermediate-level wastes is presented. Chemical, microbiological, radiolytic and thermal reactions are considered for both unconditioned wastes and wastes conditioned in cement, or bitumen, or polymer. Possible reaction mechanisms are identified and the effects of temperature and pressure are evaluated. Estimations of the production of combustible gases (which also have the potential to form explosive mixtures) have been taken from the literature. The implications of gas production for pressurisation (and possible rupture) of waste drums and of a repository are assessed. Waste-treatment schemes for the reduction of gas-generation capacity of several waste-types are highlighted. Recommendations for further work are summarised. (author)

Reevaluation of Vitrified High-Level Waste Form Criteria for Potential Cost Savings at the Defense Waste Processing Facility - 13598

Energy Technology Data Exchange (ETDEWEB)

Ray, J.W. [Savannah River Remediation (United States); Marra, S.L.; Herman, C.C. [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)

2013-07-01

At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a durable borosilicate glass since 1996. Currently the DWPF has poured over 3,500 canisters, all of which are compliant with the U. S. Department of Energy's (DOE) Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms (WAPS) and therefore ready to be shipped to a federal geologic repository for permanent disposal. Due to DOE petitioning to withdraw the Yucca Mountain License Application (LA) from the Nuclear Regulatory Commission (NRC) in 2010 and thus no clear disposal path for SRS canistered waste forms, there are opportunities for cost savings with future canister production at DWPF and other DOE producer sites by reevaluating high-level waste form requirements and compliance strategies and reducing/eliminating those that will not negatively impact the quality of the canistered waste form. (authors)

Sources, production rates and characteristics of ERDA low-level wastes

International Nuclear Information System (INIS)

Dieckhoner, J.E.

1979-01-01

In recent critical reviews of the long-standing practice of disposing of solid non-high-level radioactive waste by shallow earth burial, one recurring identified need was for better source-term information. As the major employer of this particular radioactive waste management technique for the past 30 years, ERDA recognizes the value of this type of information and has systematically collected it. The system used by the AEC and ERDA in the past was admittedly cumbersome, so in FY 1976 an improved, automated information management system was developed. This new system, called SWIMS (Solid Waste Information Management System), was designed to replace the older system and accept more detailed information from all ERDA solid, non-high-level radioactive waste generation, retrievable storage and shallow land burial activities. In FY 1977, SWIMS is in a trial phase in which modifications and clarifications are being made. In FY 1978, it will be fully operational. This paper presents data concerning the sources and characteristics of waste generated by ERDA facilities. Information on the cumulative status of ERDA's waste is presented, along with a comparison of the types of data collected under the old system and the new system

Effect of Paper Waste Products as a Litter Material on Broiler Performance

Directory of Open Access Journals (Sweden)

Serdar Özlü

2017-12-01

Full Text Available This study conducted to determine the possibilities of using the paper waste products as a litter material in broiler production. A total of 468 Ross 308 broilers were used in this experiment. Litter materials were rice hulls (RH, waste paper (WP and mix of them (50 % RH + 50 % WP. BW was approximately 60 g heavier in waste paper group compare to other two litter groups at 42d of age. Type of litter material had no significant effects on feed conversion ratio, livability and leg defect. Therefore, paper waste products have potential as an alternative litter material for broiler production.

Managing plastic waste in East Africa: Niche innovations in plastic production and solid waste

NARCIS (Netherlands)

Ombis, L.O.; Vliet, van B.J.M.; Mol, A.P.J.

2015-01-01

This paper assesses the uptake of environmental innovation practices to cope with plastic waste in Kenyan urban centres at the interface of solid waste management and plastic production systems. The Multi Level Perspective on Technological Transitions is used to evaluate 7 innovation pathways of

Production waste analysis using value stream mapping and waste assessment model in a handwritten batik industry

Directory of Open Access Journals (Sweden)

Marifa Putri Citra

2018-01-01

Full Text Available Batik is one of Indonesian cultural heritage that confirmed by United Nations of Educational, Scientific, and Cultural Organization (UNESCO on October 2009. This legal confirmation improves the number of batik industry from many regions based its local unique characteristic. The increasing number of batik SMEs in Indonesia requires a strategy that can create competitive advantage. This strategy can be done by reducing production waste. One of Indonesian batik SMEs is SME Batik CM located in Yogyakarta. There are several problems that occur in the industry, i.e. length of the production process, spots on Batik and excessive raw materials inventory. Based on that problems, this research is done by applying lean manufacturing concept using value stream mapping (VSM method to evaluate production wastes. Based on the result of the research, there are seven types of production waste: overproduction (9,62%, inventory (17,3%, defect (23,08%, motion (9,62%, transportation (9,62%, Over processing (9,62% and waiting (21,15%. Process improvement is done to reduce the highest waste, defect, using quality filter mapping (QFM.

OPTIMIZATION OF VEGETABLE WASTES FOR LACTIC ACID PRODUCTION: A LABORATORY SCALE APPROACH

Directory of Open Access Journals (Sweden)

Sailaja Daharbha

2015-04-01

Full Text Available Vegetables wastes are organic materials which are not utilized as vegetables and are discarded at all stages of production, processing and marketing. These wastes form a major part of municipal solid wastes and are cause of foul smell and growth of microorganisms due to their high organic contents. The vegetable wastes can be utilized in many different ways to produces different products. We have shown that they can be utilized for production of lactic acid using anaerobic digestion. The 2nd day was the optimum day for recovery of lactic acid while 1:1 ratio of slurry and water was found to the best ratio for production of lactic acid from vegetable wastes. Effect of salts on lactic acid was also studied and it was found that the production decreased in all the concentrations of salts.

Approaches to gaining public acceptance of repository siting

International Nuclear Information System (INIS)

Numark, N.J.; Wonder, E.F.

1989-01-01

An eight-country survey reveals a diversity of strategies that have been followed for siting radioactive waste repositories, as well as a range of levels of public acceptance of siting efforts. Although the strategies are not necessarily interchangeable from country to country, certain inferences may be drawn from worldwide siting experience regarding ways to maximize public acceptance. Furthermore, waste management organizations in these countries have placed varying amounts of stock in technical review by outside experts and in a range of communications strategies as means of improving public acceptance. Our survey of worldwide experience also allows some general observations to be made regarding the effectiveness of these efforts. Combining a strategy that elevates public acceptance to part of the overall mission of siting a waste management facility with strategies for appropriate communications and external technical review may be necessary and sufficient for gaining improvements in public acceptance of proposed repository sites

Improving societal acceptance of rad waste management policy decisions: an approach based on complex intelligence

International Nuclear Information System (INIS)

Rao, Suman

2008-01-01

In today's context elaborate public participation exercises are conducted around the world to elicit and incorporate societal risk perceptions into nuclear policy Decision-Making. However, on many occasions, such as in the case of rad waste management, the society remains unconvinced about these decisions. This naturally leads to the questions: are techniques for incorporating societal risk perceptions into the rad waste policy decision making processes sufficiently mature? How could societal risk perceptions and legal normative principles be better integrated in order to render the decisions more equitable and convincing to society? Based on guidance from socio-psychological research this paper postulates that a critical factor for gaining/improving societal acceptance is the quality and adequacy of criteria for option evaluation that are used in the policy decision making. After surveying three rad waste public participation cases, the paper identifies key lacunae in criteria abstraction processes as currently practiced. A new policy decision support model CIRDA: Complex Intelligent Risk Discourse Abstraction model that is based on the heuristic of Risk-Risk Analysis is proposed to overcome these lacunae. CIRDA's functionality of rad waste policy decision making is modelled as a policy decision-making Abstract Intelligent Agent and the agent program/abstraction mappings are presented. CIRDA is then applied to a live (U.K.) rad waste management case and the advantages of this method as compared to the Value Tree Method as practiced in the GB case are demonstrated. (author)

Lean production design using value stream mapping and ergonomics approach for waste elimination on buffing panel upright process

Science.gov (United States)

Suryoputro, M. R.; Sari, A. D.; Burhanudin, R.; Sugarindra, M.

2017-12-01

This study discussed the implementation of ergonomics and value stream mapping issues to reduce the existing waste in the process of buffing upright panel in the XYZ music manufacturing company. Aimed to identify the 9 waste based on the identification in terms of production processes and ergonomic factors, namely environmental health and safety, defects, overproduction, waiting, not utilizing employee knowledge skill and ability, transportation, inventory, motion, and excess process. In addition, ergonomics factors were identified, for example posture using REBA, job safety analysis, and physical workload. This study results indicated that the process is having 21.4% of the potential dangers that could not be accepted and thus potentially lead to lost time. Continued with the physical workload, the score of % cardiovascular load value is still below 30%, which means that the physical workload is normal and allows the addition of work. Meanwhile, in the calculation of posture investigation, the REBA resulted that there was a motion waste identified on the edge buff machine and ryoto with the score of 10 and 8. In conclusion, the results shown that there were 20 overall waste produced, then thus waste were reduced based on the identification and discussion of proposed improvements.

Acceptance, Tolerance, Participation

International Nuclear Information System (INIS)