10 CFR 72.2 - Scope.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Scope. 72.2 Section 72.2 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General Provisions § 72.2 Scope. (a) Except...

Scoping studies to reduce ICPP high-level radioactive waste volumes for final disposal

International Nuclear Information System (INIS)

Knecht, D.A.; Berreth, J.R.; Chipman, N.A.; Cole, H.S.; Geczi, L.S.; Kerr, W.B.; Staples, B.A.

1985-08-01

This report presents the results of scoping studies carried out to determine the feasibility of the following candidate options to reduce high-level waste volume: (1) low-fluoride, low-volume glass, (2) glass-ceramic and ceramic, (3) Modified Zirflex, (4) inerts removal by neutralization, and (5) modified Fluorinel processes. The results of the scoping studies show that the glass-ceramic/ceramic waste forms and neutralization process with potential HLW volume reductions ranging from 60 to 80% appear feasible, based on laboratory-scale tests. The presently used Fluorinel process modified by reducing HF usage also appears to be feasible and could result in up to a 10% potential volume reduction. If the current process start-up tests verify the practicality, reduced HF usage will be implemented. The low-volume glass and Modified Zirflex processes may also be feasible, based on laboratory tests, but would require significantly more process development and/or modifications and could result in only a 20 to 30% potential volume reduction. Based on these scoping studies, it is recommended that (1) the glass-ceramic/ceramic and neutralization processes be developed further, (2) reduced HF use for the Modified Fluorinel process be implemented as soon as practical and other options reducing chemical usage for criticality control be evaluated, (3) basic development for the glass process be continued as a back-up technology, and (4) laboratory-scale radioactive fuel dissolution testing for the Modified Zirflex process be completed with further process development discontinued unless needed in the future

Section 10: Ground Water - Waste Characteristics & Targets

Science.gov (United States)

HRS Training. The waste characteristics factor category in the ground water pathway is made up of two components: the toxicity/mobility of the most hazardous substance associated with the site and the hazardous waste quantity at the site.

Seismic scoping evaluation of high level liquid waste tank vaults at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Hashimoto, P.S.; Uldrich, E.D.; McGee, W.D.

1991-01-01

A seismic scoping evaluation of buried vaults enclosing high level liquid waste storage tanks at the Idaho Chemical Processing Plant has been performed. The objective of this evaluation was to scope out which of the vaults could be demonstrated to be seismically adequate against the Safe Shutdown Earthquake (SSE). Using approximate analytical methods, earthquake experience data, and engineering judgement, this study determined that one vault configuration would be expected to meet ICPP seismic design criteria, one would not be considered seismically adequate against the SSE, and one could be shown to be seismically adequate against the SSE using nonlinear analysis

Spent fuel and radioactive-waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1982-10-01

Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy radioactive wastes were compiled, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated over the next 40 years, and characteristics of these materials are also presented, based on a present DOE/EIA projection of US commercial nuclear power growth and expected defense-related and industrial and institutional activities. Materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, remedial action waste, active uranium mill tailings, airborne waste, and decommissioning. For each category, current and projected inventories are given through the year 2020. The land usage requirements are given for storage/disposal of low-level and transuranic wastes, and for the present inventories of inactive uranium mill tailings. For each waste category the radioactivity and thermal power are calculated. Isotopic compositions and cost data are given for each waste type and for spent fuel

Spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1984-09-01

Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy (DOE) radioactive wastes were compiled through December 31, 1983, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated over the next 37 years and characteristics of these materials are also presented, consistent with the latest DOE/Energy Information Administration (EIA) or projection of US commercial nuclear power growth and expected defense-related and private industrial and institutional activities. Materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, airborne waste, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated, based on reported or calculated isotopic compositions. 48 figures, 107 tables

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.

A comparison of high-level waste form characteristics

International Nuclear Information System (INIS)

Salmon, R.; Notz, K.J.

1991-01-01

The US DOE is responsible for the eventual disposal in a repository of spent fuels, high-level waste (HLW) and other radioactive wastes that may require long-term isolation. This includes light-water reactor (LWR) spent fuel and immobilized HLW as the two major sources, plus other forms including non-LWR spent fuels and miscellaneous sources (such as activated metals in the Greater-Than-Class-C category). The Characteristics Data Base, sponsored by DOE's Office of Civilian Radioactive Waste Management (OCRWM), was created to systematically tabulate the technical characteristics of these materials. Data are presented here on the immobilized HLW forms that are expected to be produced between now and 2020

Characteristics of high-level radioactive waste forms for their disposal

International Nuclear Information System (INIS)

Kim, Seung Soo; Chun, Kwan Sik; Kang, Chul Hyung

2000-12-01

In order to develop a deep geological repository for a high-level radioactive waste coming from reprocessing of spent nuclear fuels discharged from our domestic nuclear power plants, the the required characteristics of waste form are dependent upon a solidifying medium and the amount of waste loading in the medium. And so, by the comparative analysis of the characteristics of various waste forms developed up to the present, a suitable medium is recommended.The overall characteristics of the latter is much better than those of the former, but the change of the properties due to an amorphysation by radiation exposure and its thermal expansion has not been clearly identified yet. And its process has not been commercialized. However, the overall properties of the borosilicate glass waste forms are acceptable for their disposal, their production cost is reasonable and their processes have already been commercialized. And plenty informations of their characteristics and operational experiences have been accumulated. Consequently, it is recommended that a suitable medium solidifying the HLW is a borosilicate glass and its composition for the identification of a reference waste form would be based on the glass frit of R7T7

Degradation characteristics of waste polyurethane by radiation

Energy Technology Data Exchange (ETDEWEB)

Park, Jong Seok; Ahn, Sung Jun; Gwon Hui Jeong; Jeong, Sung In; Nho, Young Chang; Lim, Youn Mook [Research Division for Industry and Environment, Korea Atomic Energy Research Institute, Jeongeup (Korea, Republic of)

2017-06-15

Polyurethane (PU) is a very popular polymer that is used in a variety of applications due to its good mechanical, thermal, and chemical properties. However, waste PU recycling has received significant attention due to environmental issues. The aim of this work was to investigate the degradation characteristics of waste PU to recycle. Degradation of waste PU was carried out using a radiation techniques. Waste PUs were exposed to a gamma {sup 60}Co sources. To verify degradation, the irradiated PUs were characterized using FT-IR, gel permeation chromatography (GPC), and their thermal/mechanical properties are reported. When the radiation dose was 500 kGy, the molecular weight of the waste PU drastically decreased. Also, the mechanical properties of waste PU were approximately 4 times lower than those of non-irradiated PU. This study has confirmed the possibility of making fine particle of waste PU for recycling through radiation degradation techniques.

10 CFR 61.58 - Alternative requirements for waste classification and characteristics.

Science.gov (United States)

2010-01-01

... characteristics. 61.58 Section 61.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR... Alternative requirements for waste classification and characteristics. The Commission may, upon request or on its own initiative, authorize other provisions for the classification and characteristics of waste on...

Pretreatment Characteristics of Waste Oak Wood by Ammonia Percolation

Science.gov (United States)

Kim, Jun-Seok; Kim, Hyunjoon; Lee, Jin-Suk; Lee, Joon-Pyo; Park, Soon-Chul

A log of waste oak wood collected from a Korean mushroom farm has been tested for ammonia percolation pretreatment. The waste log has different physical characteristics from that of virgin oak wood. The density of the waste wood was 30% lower than that of virgin oak wood. However, there is little difference in the chemical compositions between the woods. Due to the difference in physical characteristics, the optimal pretreatment conditions were also quite different. While for waste oak the optimum temperature was determined to be 130°C, for virgin oak wood the optimum pretreatment was only achieved at 170°C. Presoaking for 12 h with ammonia solution before pretreatment was helpful to increase the delignification efficiency.

Characteristics of Indigenous primary health care service delivery models: a systematic scoping review.

Science.gov (United States)

Harfield, Stephen G; Davy, Carol; McArthur, Alexa; Munn, Zachary; Brown, Alex; Brown, Ngiare

2018-01-25

Indigenous populations have poorer health outcomes compared to their non-Indigenous counterparts. The evolution of Indigenous primary health care services arose from mainstream health services being unable to adequately meet the needs of Indigenous communities and Indigenous peoples often being excluded and marginalised from mainstream health services. Part of the solution has been to establish Indigenous specific primary health care services, for and managed by Indigenous peoples. There are a number of reasons why Indigenous primary health care services are more likely than mainstream services to improve the health of Indigenous communities. Their success is partly due to the fact that they often provide comprehensive programs that incorporate treatment and management, prevention and health promotion, as well as addressing the social determinants of health. However, there are gaps in the evidence base including the characteristics that contribute to the success of Indigenous primary health care services in providing comprehensive primary health care. This systematic scoping review aims to identify the characteristics of Indigenous primary health care service delivery models. This systematic scoping review was led by an Aboriginal researcher, using the Joanna Briggs Institute Scoping Review Methodology. All published peer-reviewed and grey literature indexed in PubMed, EBSCO CINAHL, Embase, Informit, Mednar, and Trove databases from September 1978 to May 2015 were reviewed for inclusion. Studies were included if they describe the characteristics of service delivery models implemented within an Indigenous primary health care service. Sixty-two studies met the inclusion criteria. Data were extracted and then thematically analysed to identify the characteristics of Indigenous PHC service delivery models. Culture was the most prominent characteristic underpinning all of the other seven characteristics which were identified - accessible health services, community

1995 solid waste 30-year characteristics volume summary

International Nuclear Information System (INIS)

Templeton, K.J.; DeForest, T.J.; Rice, G.I.; Valero, O.J.

1995-10-01

The Hanford Site has been designated by the US Department of Energy (DOE) to store, treat, and dispose of solid waste received from both onsite and offsite generators. This waste is currently or planned to be generated from ongoing operations, maintenance and deactivation activities, decontamination and decommissioning (D ampersand D) of facilities, and environmental restoration (ER) activities. This document, prepared by Pacific Northwest Laboratory (PNL) under the direction of Westinghouse Hanford Company (WHC), describes the characteristics of the waste to be shipped to Hanford's SWOC. The physical waste forms and hazardous constituents are described for the low-level mixed waste (LLMW) and the transuranic - transuranic mixed waste (TWunderscoreTRUM)

HANFORD SITE SOLID WASTE MANAGEMENT ENVIRONMENTAL IMPACT STATEMENT TECHNICAL INFORMATION DOCUMENT [SEC 1 THRU 4

International Nuclear Information System (INIS)

FRITZ, L.L.

2004-01-01

This Technical Information Document (TID) provides engineering data to support DOE/EIS-0286, ''Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement''. Assumptions and waste volumes used to calculate engineering data are also provided in this document. This chapter provides a brief description of: the Solid Waste Management Program (including a description of waste types and known characteristics of waste covered under the program), the Hanford Site (including a general discussion of the operating areas), and the alternatives analyzed. The Hanford Site Solid Waste Management Program and DOE/EIS-0286 address solid radioactive waste types generated by various activities from both onsite and offsite generators. The Environmental Restoration (ER) waste management activities are not within the scope of DOE/EIS-0286 or this TID. Activities for processing and disposal of immobilized low-activity waste (ILAW) are not within the scope of the Solid Waste Management Program and this TID

Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2, Chapter 3.0, Waste characteristics supplemental information; Volume 1

International Nuclear Information System (INIS)

1993-01-01

This report contains supplemental information concerning waste characteristics for numerous nonradioactive waste materials. Uniform hazardous waste manifests are included for routine as well as nonroutine waste streams. The manifests contain the following information: waste disposal analysis; general instructions; waste destination; and transportation representatives

Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2, Chapter 3.0, Waste characteristics supplemental information; Volume 2

International Nuclear Information System (INIS)

1993-01-01

This report contains supplemental information concerning waste characteristics for numerous nonradioactive waste materials. Uniform hazardous waste manifests are included for routine as well as nonroutine waste streams. The manifests contain the following information: waste disposal analysis; general instructions; waste destination; and transportation representatives

Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2, Chapter 3.0, Waste characteristics supplemental information; Volume 3

International Nuclear Information System (INIS)

1993-01-01

This report contains supplemental information concerning waste characteristics for numerous nonradioactive waste materials. Uniform hazardous waste manifests are included for routine as well as nonroutine waste streams. The manifests contain the following information: waste disposal analysis; general instructions; waste destination; and transportation representatives

Spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1983-09-01

Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy radioactive wastes were compiled through December 31, 1982, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated over the next 40 years and characteristics of these materials are also presented, based on the latest DOE/EIA projection of US commercial nuclear power growth and expected defense-related and industrial and institutional activities. Materials considered, on a chapter-by-chapter bases, are: spent fuel, high-level waste, transuranic waste, low-level waste, active uranium mill tailings, airborne waste, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated, based on reported or calculated isotopic compositions. One chapter gives broad, summary data on the costs of spent fuel and radioactive waste management and disposal to provide an economic perspective. This chapter is not intended as a definitive guide, but it is a source of reasonable, order-of-magnitude costs and also provides references to more-detailed and scenario-specific studies. An appendix on generic flowsheets and source terms used for the projections is also included

10 CFR 60.150 - Scope.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Scope. 60.150 Section 60.150 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN GEOLOGIC REPOSITORIES Quality Assurance § 60.150 Scope. As used in this part, quality assurance comprises all those planned and systematic...

10 CFR 63.141 - Scope.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Scope. 63.141 Section 63.141 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN A GEOLOGIC REPOSITORY AT YUCCA MOUNTAIN, NEVADA Quality Assurance § 63.141 Scope. As used in this part, quality assurance comprises all those...

Properties and characteristics of high-level waste glass

International Nuclear Information System (INIS)

Ross, W.A.

1977-01-01

This paper has briefly reviewed many of the characteristics and properties of high-level waste glasses. From this review, it can be noted that glass has many desirable properties for solidification of high-level wastes. The most important of these include: (1) its low leach rate; (2) the ability to tolerate large changes in waste composition; (3) the tolerance of anticipated storage temperatures; (4) its low surface area even after thermal shock or impact

Report on the workshop to review waste inventory, waste characteristics and reference site candidates

International Nuclear Information System (INIS)

1997-07-01

There is a need of co-operation among Regional Co-operative Agreement (RCA) Member States in the field of low and intermediate level waste (LILW) disposal. An integrated approach is essential for successful establishment of LILW disposal facilities in RCA Member States. This would include: a) identification of waste inventory and characteristics; b) guidelines for implementation of LILW disposal; c) regulatory guidelines; d) safety assessment; e) quality assurance; and f) public acceptance. This project will focus on technical issues. The overall objective of the project, established in the project formulation meeting, is to assist RCA Member States in establishing national disposal activities for radioactive waste from nuclear applications by providing expert advice and training on techniques and methodology associated with planning and establishment of disposal facilities and to obtain improved knowledge of key staff members for the implementation of LILW disposal. The purpose of this workshop was to identify waste inventories, waste characteristics, site characteristics (generic or site specific) for disposal of LILW in RCA Member States of the project and identify conceptual reference site conditions and consider reference repository concepts preliminarily. Also the workshop was to establish an action plan of the next step. The workshop was held in Shanghai, China from 7 to 9 July 1997 and attended by 7 countries, i.e. Australia, China, Indonesia, Japan, Republic of Korea, Sri Lanka and Thailand. Refs, figs, tabs

Probe into Environmental Kuznets Characteristics and Causes of Wastewater,Waste Gas, and Solid Wastes in Wuhan City

Institute of Scientific and Technical Information of China (English)

刘耀彬; 李仁东

2004-01-01

Environmental Kuznets characteristics and causes of waste water, waste gas, and solid wastes in Wuhan city was researched; By comparing the variation of "three wastes", i.e. waste water, waste gas, and solid wastes, the model between standardized per capita GDP and values of "three wastes" discharge was established and the causes were analyzed based on the theory of environmental economics. The results show that 1) the total amount is fluctuantly increasing, but the discharges of the three kinds are temporarily different, 2) the curve conforms to the three-power function, in which the curve descends from 1985 to 1994, and the curve preliminary shows the environmental Kuznets characteristics from 1995 to 2001, 3) the simulated calculation illustrates that the turning point of this environmental Kuznets curve would be over 25007.25 Yuan per caprta, and 4) the economic development, changing of industry structure, energy resource structure, and environmental policies are the main factors leading to the Environmental Kuznets Curve in Wuhan city.

MANAGEING THE RETRIEVAL RISK OF BURIED TRANSURANIC (TRU) WASTE WITH UNIQUE CHARACTERISTICS

International Nuclear Information System (INIS)

WOJTASEK, R.D.; GREENWELL, R.D.

2005-01-01

United States-Department of Energy (DOE) sites that store transuranic (TRU) waste are almost certain to encounter waste packages with characteristics that are so unique as to warrant special precautions for retrieval. At the Hanford Site, a subgroup of stored TRU waste (12 drums) had special considerations due to the radioactive source content of plutonium oxide (PuO 2 ), and the potential for high heat generation, pressurization, criticality, and high radiation. These characteristics bear on the approach to safely retrieve, overpack, vent, store, and transport the waste package. Because of the potential risk to personnel, contingency planning for unexpected conditions played an effective roll in work planning and in preparing workers for the field inspection activity. As a result, the integrity inspections successfully confirmed waste package configuration and waste confinement without experiencing any perturbations due to unanticipated packaging conditions. This paper discusses the engineering and field approach to managing the risk of retrieving TRU waste with unique characteristics

Scoping evaluation of the technical capabilities of DOE sites for disposal of hazardous metals in mixed low-level waste

International Nuclear Information System (INIS)

Gruebel, M.M.; Waters, R.D.; Langkopf, B.S.

1997-05-01

A team of analysts designed and conducted a scoping evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of the hazardous metals in mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Eight hazardous metals were evaluated: arsenic, barium, cadmium, chromium, lead, mercury, selenium, and silver. The analysis considered transport only through the groundwater pathway. The results are reported as site-specific estimates of maximum concentrations of each hazardous metal in treated mixed low-level waste that do not exceed the performance measures established for the analysis. Also reported are site-specific estimates of travel times of each hazardous metal to the point of compliance

Characteristics of radioactive waste streams generated in HTGR fuel reprocessing

International Nuclear Information System (INIS)

Lin, K.H.

1976-01-01

Results are presented of a study concerned with identification and characterization of radioactive waste streams from an HTGR fuel reprocessing plant. Approximate quantities of individual waste streams as well as pertinent characteristics of selected streams have been estimated. Most of the waste streams are unique to HTGR fuel reprocessing. However, waste streams from the solvent extraction system and from the plant facilities do not differ greatly from the corresponding LWR fuel reprocessing wastes

Influencing factors of domestic waste characteristics in rural areas of developing countries.

Science.gov (United States)

Han, Zhiyong; Liu, Yong; Zhong, Min; Shi, Guozhong; Li, Qibin; Zeng, Dan; Zhang, Yu; Fei, Yongqiang; Xie, Yanhua

2018-02-01

Waste management in rural areas has become a major challenge for governments of developing countries. The success of waste management decisions directly lies in the accuracy and reliability of the data on which choices are based; many factors influence these data. Here, we examined the factors influencing domestic waste in rural areas of developing countries (RADIC), using both field surveys and by reviewing previous literature. The social factors included population, education and culture. There was a positive linear relationship between waste generation amount and population size (R 2  = 0.9405). Environmental education, training and demonstration projects played a positive role in improving people's awareness of the benefits of recycling and reducing waste. Traditional and national cultures, consumption and living habits contributed to variations in the generation and composition of domestic waste. Generally, practices related to conservation of and reverence for nature and green consumption encourage people to reduce, reuse and recycle waste in their daily life. Economic factors included household income and expenditure, energy and fuel structure, and types of industry that occurred in villages. A Kuznets inverted "U" curve relationship existed between domestic waste generation and people's income in rural areas of China. However, the waste generation rate had a linear relationship with the gross national income per capita in RADIC. The composition, bulk density and calorific value of domestic waste were variously affected by the energy and fuel structure and the types of industry that occurred. The natural factors included geography and climate (including rainfall, humidity, temperature and harvest seasons). The moisture content of waste was directly influenced by rainfall and humidity. Temperature affected waste characteristics by influencing residential heating modes. The waste characteristics were also influenced by the mixing of agricultural and

A study on characterization and evaluation methodologies of radioactive waste forms for safe disposal

Energy Technology Data Exchange (ETDEWEB)

Seo, Y. C.; Lee, G. S.; Kim, G. J.; Nam, H.; Seok, J. H. [Yonsei Univ., Seoul (Korea, Republic of)

2004-02-15

The contents and scope of the study are summarized as follows : elicitation of significant items for characteristic assessment about stability analysis of radioactive waste forms for safe disposal, compressive strength, free water, leaching rate, and weatherability. Suggestion of assessment methods through the characteristic test of waste forms, comparison of assessment methods and suggestion of suitable testing methods about the above stated 4 items. Assessment modeling development for long-term stability of radioactive waste forms, weatherometric test of waste forms, expectation modeling development through VOM(Valance-Oxygen Model). Suggestion of determination standard together assessment testing methods and description about the standard. Explanation to be suitable guideline and regulation of waste handling and acceptance.

Scoping survey of perceived concerns, issues, and problems for near-surface disposal of FUSRAP waste

International Nuclear Information System (INIS)

Robinson, J.E.; Gilbert, T.L.

1982-12-01

This report is a scoping summary of concerns, issues, and perceived problems for near-surface disposal of radioactive waste, based on a survey of the current literature. Near-surface disposal means land burial in or within 15 to 20 m of the earth's surface. It includes shallow land burial (burial in trenches, typically about 6 m deep with a 2-m cap and cover) and some intermediate-depth land burial (e.g., trenches and cap similar to shallow land burial, but placed below 10 to 15 m of clean soil). Proposed solutions to anticipated problems also are discussed. The purpose of the report is to provide a better basis for identifying and evaluating the environmental impacts and related factors that must be analyzed and compared in assessing candidate near-surface disposal sites for FUSRAP waste. FUSRAP wastes are of diverse types, and their classification for regulatory purposes is not yet fixed. Most of it may be characterized as low-activity bulk solid waste, and is similar to mill tailings, but with somewhat lower average specific activity. It may also qualify as Class A segregated waste under the proposed 10 CFR 61 rules, but the parent radionuclides of concern in FUSRAP (primarily U-238 and Th-232) have longer half-lives than do the radionuclides of concern in most low-level waste. Most of the references reviewed deal with low-level waste or mill tailings, since there is as yet very little literature in the public domain on FUSRAP per se

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

International Nuclear Information System (INIS)

Cunnane, J.C.

1994-03-01

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

Technology for commercial radioactive waste management

International Nuclear Information System (INIS)

1979-05-01

The scope of this report is limited to technology for management of past-fission wastes produced in the commercial nuclear power light water reactor fuel cycle. Management of spent fuel (as a waste), high-level and other transuranic wastes, and gaseous wastes are characterized. Non-transuranic wastes are described, but management of these wastes, except for gaseous wastes, is excluded from the scope of this report. Volume 1 contains the summary and the bases and background information

Evaluating and controlling the characteristics of the nuclear waste in the FWMS using waste stream analysis model

International Nuclear Information System (INIS)

Andress, D.; McLeod, N.B.; Joy, D.S.

1990-01-01

The Waste Stream Analysis (WSA) Model is used by the Department of Energy to model the item and location dependent properties of the nuclear waste stream in the Federal Waste Managements System and at utility spent fuel storage facilities. WSA can simulate a wide variety of FWMS configurations and operating strategies and can select and sequence spent fuel for optimal efficiency in the FWMS while minimizing adverse impact on the utility sector. WSA tracks each assembly from the time of discharge to ultimate geologic disposal including all shipping cask and waste package loadings and both at-reactor and FWMS consolidation. WSA selects the highest capacity shipping cask or waste package that does not violate external dose rate or heat limitations for a group of spent fuel assemblies to be containerized. This paper presents an overview of the Waste Stream Analysis Model and a number of key results from a set of coordinated SIMS runs, which illustrates both the impact of waste characteristics on system performance and the ability to control waste characteristics by use of selection and sequencing strategies. 7 refs., 6 figs

Fundamental characteristics of input waste of small MSW incinerators in Korea.

Science.gov (United States)

Choi, Ki-In; Lee, Suk-Hui; Lee, Dong-Hoon; Osako, Masahiro

2008-11-01

Waste incineration in a small incinerator is a simple and convenient way of treating waste discharged from small areas or from large facilities and buildings such as business centers, marketplaces, factories, and military units. Despite their ostensible advantages, however, many small incinerators frequently suffer from serious problems, e.g., unsystematic waste feeding, unstable combustion, deficient air pollution control devices, and consequently, environmental pollution. To obtain a better understanding of the characterization of wastes in small incinerators, we investigated a series of fundamental characteristics, i.e., physical composition, bulk density, proximate and ultimate analysis, potential energy content, and so on. The main waste components in small incinerators were identified as paper and plastic; the proportion of food waste was less than that in large incinerators. Especially, a low ratio of food waste had a strong influence on other waste characteristics, e.g., lower moisture content and bulk density, and higher potential energy. On the other hand, in contrast with that of HCl, there was no distinguishable linear relationship between Cl content in waste and PCDD/DF concentration in combustion gas.

Preliminary waste form characteristics report Version 1.0. Revision 1

International Nuclear Information System (INIS)

Stout, R.B.; Leider, H.R.

1991-01-01

This report focuses on radioactive waste form characteristics that will be used to design a waste package and an engineered barrier system (EBS) for a suitable repository as part of the Yucca Mountain Project. The term waste form refers to irradiated reactor fuel, other high-level waste (HLW) in various physical forms, and other radioactive materials (other than HLW) which are received for emplacement in a geologic repository. Any encapsulating of stabilizing matrix is also referred to as a waste form

Leaching characteristics of copper flotation waste before and after vitrification.

Science.gov (United States)

Coruh, Semra; Ergun, Osman Nuri

2006-12-01

Copper flotation waste from copper production using a pyrometallurgical process contains toxic metals such as Cu, Zn, Co and Pb. Because of the presence of trace amounts of these highly toxic metals, copper flotation waste contributes to environmental pollution. In this study, the leaching characteristics of copper flotation waste from the Black Sea Copper Works in Samsun, Turkey have been investigated before and after vitrification. Samples obtained from the factory were subjected to toxicity tests such as the extraction procedure toxicity test (EP Tox), the toxicity characteristic leaching procedure (TCLP) and the "method A" extraction procedure of the American Society of Testing and Materials. The leaching tests showed that the content of some elements in the waste before vitrification exceed the regulatory limits and cannot be disposed of in the present form. Therefore, a stabilization or inertization treatment is necessary prior to disposal. Vitrification was found to stabilize heavy metals in the copper flotation waste successfully and leaching of these metals was largely reduced. Therefore, vitrification can be an acceptable method for disposal of copper flotation waste.

10 CFR 62.1 - Purpose and scope.

Science.gov (United States)

2010-01-01

... (42 U.S.C. 2021) to any non-Federal or regional low-level radioactive waste (LLW) disposal facility or... regional or non-Federal low-level radioactive waste disposal facilities and who submit a request to the... LOW-LEVEL WASTE DISPOSAL FACILITIES General Provisions § 62.1 Purpose and scope. (a) The regulations...

Characteristics of potential repository wastes

International Nuclear Information System (INIS)

Cowart, C.G.; Notz, K.J.

1992-10-01

This report presents the results of a fully documented peer review of DOE/RW-0184, Rev. 1, ''Characteristics of Potential Repository Wastes''. The peer review was chaired and administered by oak Ridge National Laboratory (ORNL) for the Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) and was conducted in accordance with OCRWM QA procedure QAAP 3.3 ''Peer Review'' for the purpose of quailing the document for use in OCRWM quality-affecting work. The peer reviewers selected represent a wide range of experience and knowledge particularly suitable for evaluating the subject matter. A total of 596 formal comments were documented by the seven peer review panels, and all were successfully resolved. The peers reached the conclusion that DOE/RW-0184, Rev. 1, is quality determined and suitable for use in quality-affecting work

10 CFR 60.1 - Purpose and scope.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Purpose and scope. 60.1 Section 60.1 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN GEOLOGIC REPOSITORIES General Provisions § 60.1 Purpose and scope. This part prescribes rules governing the licensing (including issuance...

10 CFR 63.1 - Purpose and scope.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Purpose and scope. 63.1 Section 63.1 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTES IN A GEOLOGIC REPOSITORY AT YUCCA MOUNTAIN, NEVADA General Provisions § 63.1 Purpose and scope. This part prescribes rules governing the...

40 CFR 268.9 - Special rules regarding wastes that exhibit a characteristic.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Special rules regarding wastes that... (CONTINUED) SOLID WASTES (CONTINUED) LAND DISPOSAL RESTRICTIONS General § 268.9 Special rules regarding wastes that exhibit a characteristic. (a) The initial generator of a solid waste must determine each EPA...

Guidelines on the scope, content, and use of comprehensive risk assessment in the management of high-level nuclear waste transportation

International Nuclear Information System (INIS)

Golding, D.; White, A.

1990-12-01

This report discusses the scope of risk assessment strategies in the management of the transport of high-level radioactive wastes. In spite of the shortcomings of probabilistic risk assessment(PRA), the Transportation Needs Assessment recommended this as the preferred methodology to assess the risks of high level nuclear waste (HLNW) transportation. A PRA also will need to heed the lessons learned from the development and application of PRA elsewhere, such as in the nuclear power industry. A set of guidelines will aid this endeavor by outlining the appropriate scope, content, and use of a risk assessment which is more responsive to the uncertainties, human-technical interactions, social forces, and iterative relationship with risk management strategies, than traditional PRAS. This more expansive definition, which encompasses but is not totally reliant on rigorous data requirements and quantitative probability estimates, we term Comprehensive Risk Assessment (CRA) Guidelines will be developed in three areas: the limitations of existing methodologies and suggested modifications; CRA as part of a flexible, effective, adaptive risk management system for HLNW transportation; and, the use of CRA in risk communication

Transuranic contaminated waste form characterization and data base

International Nuclear Information System (INIS)

McArthur, W.C.; Kniazewycz, B.G.

1980-07-01

This report outlines the sources, quantities, characteristics and treatment of transuranic wastes in the United States. This document serves as part of the data base necessary to complete preparation and initiate implementation of transuranic wastes, waste forms, waste container and packaging standards and criteria suitable for inclusion in the present NRC waste management program. No attempt is made to evaluate or analyze the suitability of one technology over another. Indeed, by the nature of this report, there is little critical evaluation or analysis of technologies because such analysis is only appropriate when evaluating a particular application or transuranic waste streams. Due to fiscal restriction, the data base is developed from a myriad of technical sources and does not necessarily contain operating experience and the current status of all technologies. Such an effort was beyond the scope of this report

Transuranic contaminated waste form characterization and data base

Energy Technology Data Exchange (ETDEWEB)

McArthur, W.C.; Kniazewycz, B.G.

1980-07-01

This report outlines the sources, quantities, characteristics and treatment of transuranic wastes in the United States. This document serves as part of the data base necessary to complete preparation and initiate implementation of transuranic wastes, waste forms, waste container and packaging standards and criteria suitable for inclusion in the present NRC waste management program. No attempt is made to evaluate or analyze the suitability of one technology over another. Indeed, by the nature of this report, there is little critical evaluation or analysis of technologies because such analysis is only appropriate when evaluating a particular application or transuranic waste streams. Due to fiscal restriction, the data base is developed from a myriad of technical sources and does not necessarily contain operating experience and the current status of all technologies. Such an effort was beyond the scope of this report.

40 CFR 261.10 - Criteria for identifying the characteristics of hazardous waste.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Criteria for identifying the characteristics of hazardous waste. 261.10 Section 261.10 Protection of Environment ENVIRONMENTAL PROTECTION... solid waste through their knowledge of their waste. (b) [Reserved] ...

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.

40 CFR 260.1 - Purpose, scope, and applicability.

Science.gov (United States)

2010-07-01

....1 Section 260.1 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) HAZARDOUS WASTE MANAGEMENT SYSTEM: GENERAL General § 260.1 Purpose, scope, and applicability. (a) This part provides definitions of terms, general standards, and overview information applicable to...

Parametric study of geohydrologic performance characteristics for geologic waste repositories

International Nuclear Information System (INIS)

Bailey, C.E.; Marine, I.W.

1980-11-01

One of the major objectives of the National Waste Terminal Storage Program is to identify potential geologic sites for storage and isolation of radioactive waste (and possibly irradiated fuel). Potential sites for the storage and isolation of radioactive waste or spent fuel in a geologic rock unit are being carefully evaluated to ensure that radionuclides from the stored waste or fuel will never appear in the biosphere in amounts that would constitute a hazard to the health and safety of the public. The objective of this report is to quantify and present in graphical form the effects of significant geohydrologic and other performance characteristics that would influence the movement of radionuclides from a storage site in a rock unit to the biosphere. The effort in this study was focused on transport by groundwater because that is the most likely method of radionuclide escape. Graphs of the major performance characteristics that influence the transport of radionuclides from a repository to the biosphere by groundwater are presented. The major characteristics addressed are radioactive decay, leach rate, hydraulic conductivity, porosity, groundwater gradient, hydrodynamic dispersion, ion exchange, and distance to the biosphere. These major performance characteristics are combind with each other and with the results of certain other combinations and presented in graphical form to provide the interrelationships of values measured during field studies. The graphical form of presentation should be useful in the screening process of site selection. An appendix illustrates the use of these graphs to assess the suitability of a site

Hanford Site Waste Management Plan

International Nuclear Information System (INIS)

1988-12-01

The Hanford Site Waste Management Plan (HWMP) was prepared in accordance with the outline and format described in the US Department of Energy Orders. The HWMP presents the actions, schedules, and projected costs associated with the management and disposal of Hanford defense wastes, both radioactive and hazardous. The HWMP addresses the Waste Management Program. It does not include the Environmental Restoration Program, itself divided into the Environmental Restoration Remedial Action Program and the Decontamination and Decommissioning Program. The executive summary provides the basis for the plans, schedules, and costs within the scope of the Waste Management Program at Hanford. It summarizes fiscal year (FY) 1988 including the principal issues and the degree to which planned activities were accomplished. It further provides a forecast of FY 1989 including significant milestones. Section 1 provides general information for the Hanford Site including the organization and administration associated with the Waste Management Program and a description of the Site focusing on waste management operations. Section 2 and Section 3 describe radioactive and mixed waste management operations and hazardous waste management, respectively. Each section includes descriptions of the waste management systems and facilities, the characteristics of the wastes managed, and a discussion of the future direction of operations

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

Characteristics Data Base: Programmer's guide to the High-Level Waste Data Base

International Nuclear Information System (INIS)

Jones, K.E.; Salmon, R.

1990-08-01

The High-Level Waste Data Base is a menu-driven PC data base developed as part of OCRWM's technical data base on the characteristics of potential repository wastes, which also includes spent fuel and other materials. This programmer's guide completes the documentation for the High-Level Waste Data Base, the user's guide having been published previously. 3 figs

10 CFR 2.700 - Scope of subpart G.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Scope of subpart G. 2.700 Section 2.700 Energy NUCLEAR... Formal Adjudications § 2.700 Scope of subpart G. The provisions of this subpart apply to and supplement... authorization for high-level radioactive waste repository noticed under §§ 2.101(f)(8) or 2.105(a)(5...

Integrated data base for 1988: Spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1988-09-01

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1987. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected defense-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reportd for miscellaneous, highly radioactive materials that may require geologic disposal. 89 refs., 46 figs., 104 tabs

Integrated Data Base for 1989: Spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1989-11-01

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1988. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected defense-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, commercial reactor and fuel cycle facility decommissioning waste, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous, highly radioactive materials that may require geologic disposal. 45 figs., 119 tabs

Impacts of the proposed program approach on waste stream characteristics

International Nuclear Information System (INIS)

King, J.F.; Fleming, M.E.

1995-01-01

The evolution of the U.S. Department of Energy's Civilian Radioactive Waste Management System (CRWMS) over the past few years has led to significant changes in key system scenario assumption. This paper describes the effects of two recent changes on waste stream characteristics focusing primarily on repository impacts. First, the multi-purpose canister (MPC) concept has been included in the Program baseline. The change from a bare fuel system to one including an MPC-based system forces the fuel assemblies initially loaded together in MPCs to remain together throughout the system. Second, current system analyses also assume a system without a monitored retrievable storage (MRS), with the understanding that an MRS would be reincorporated if a site becomes available. Together these two changes have significant impacts on waste stream characteristics. Those two changes create a class of scenarios referred to generally as Program Approach (PA) scenarios. Scenarios based on the previously assumed system, bare fuel with an MRS, are referred to here as the Previous Reference (PR) system scenarios. The analysis compares scenarios with otherwise consistent assumptions and presents summary comparisons. The number of disposal containers and the waste heat output are determined for eight PA and PR scenarios

Trafficking in women in Serbia and neighboring countries: Scope, characteristics and causes

Directory of Open Access Journals (Sweden)

Nikolić-Ristanović Vesna Ž.

2002-01-01

Full Text Available In this paper scope, characteristics and causes of sex trafficking in women are analyzed. The analysis considers trafficking in women in Serbia and in its direct and indirect surrounding. Available data about distribution and channels of trafficking in women, as well as about methods of recruitment, transfer and victimization of women are analyzed. Also, some of characteristics of traffickers are considered. The special chapter deals with factors that contribute to sex trafficking in women. These factors are classified in three groups: push factors, pull factors and facilitating factors. In the conclusion, the author points out the importance of data exposed in this paper for building efficient system of struggle against as well as prevention of trafficking of human beings in general, and, of sex trafficking in women, in particular.

Assessment of waste characteristics and waste management practices for the Midwest compact region:

International Nuclear Information System (INIS)

Sutherland, A.A.

1986-01-01

To define that system and optimize its components, it is necessary to know various characteristics of the LLW generated in the Midwest Compact Region. It must have projections for the annual volumes from the states in the compact to determine the size and lifetimes of waste management facilities. Information on the different volumes of the region's LLW that fall into NRC waste classes will help determine volumes of waste that may need separate disposal. Eventually, licensing a LLW disposal facility will require source terms /emdash/ quantities and concentrations of nuclides placed in the facility /emdash/ in order to conduct performance assessments. To provide the information needed to make informed decisions about the nature and size of the Midwest region's low-level waste management system, information was gathered from a number of sources. The information was placed in a computer data base to preserve it and to facilitate extracton of combinations of data. This report describes how the information was assembled and the nature of the computerized data base. It also provides a baseline characterization of the low-level waste being generated and shipped for disposal from the Midwest region in the late 1980's. 10 refs., 7 figs., 13 tabs

Waste Management Program management plan. Revision 1

International Nuclear Information System (INIS)

1997-02-01

As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management's objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL

A study on engineering characteristics of asphalt concrete using filler with recycled waste lime.

Science.gov (United States)

Sung Do, Hwang; Hee Mun, Park; Suk keun, Rhee

2008-01-01

This study focuses on determining the engineering characteristics of asphalt concrete using mineral fillers with recycled waste lime, which is a by-product of the production of soda ash (Na(2)CO(3)). The materials tested in this study were made using a 25%, 50%, 75%, and 100% mixing ratio based on the conventional mineral filler ratio to analyze the possibility of using recycled waste lime. The asphalt concretes, made of recycled waste lime, hydrated lime, and conventional asphalt concrete, were evaluated through their fundamental engineering properties such as Marshall stability, indirect tensile strength, resilient modulus, permanent deformation characteristics, moisture susceptibility, and fatigue resistance. The results indicate that the application of recycled waste lime as mineral filler improves the permanent deformation characteristics, stiffness and fatigue endurance of asphalt concrete at the wide range of temperatures. It was also determined that the mixtures with recycled waste lime showed higher resistance against stripping than conventional asphalt concrete. It was concluded from various test results that a waste lime can be used as mineral filler and, especially, can greatly improve the resistance of asphalt concrete to permanent deformation at high temperatures.

Characteristics and application potential of municipal solid waste incineration (MSWI) bottom ashes from two waste-to-energy plants

NARCIS (Netherlands)

Tang, P.; Florea, M.V.A.; Spiesz, P.R.; Brouwers, H.J.H.

2015-01-01

This study focuses on municipal solid waste incineration (MSWI) bottom ash characteristics, its heterogeneity, environmental properties, and their stability in time. The physical and chemical characteristics of bottom ashes from two plants were determined over time; results show that their

Characteristics and Generation of Household Hazardous Waste (HHW in Semarang City Indonesia

Directory of Open Access Journals (Sweden)

Fikri Elanda

2018-01-01

Full Text Available Most of Household Hazardous Waste (HHW is currently mixed with domestics waste. So that, it can impact human health and environmental quality. One important aspect in the management strategy is to determine the quantity generated and characteristics of HHW. The method used to determine the characteristics HHW refers to SNI 19-2454-2002, while the HHW generation refers to the SNI 19-3694-1994 calculated based on weight and volume. Research was conducted in four districts of Semarang. The samples used in this study were 400 families calculated based on the proportion of Slovin Formula. The characteristic of HHW in Semarang City is mainly infectious (79%, then poisonous (13%, combustible (6% and corrosive materials (2%. The quantity HHW generated is 0.01 kg/person/day equivalent with 5.1% of municipal solid waste (MSW in Semarang (linear equations : y=1,278x+82,00 (volume, y=0,216x+13,89 (weight.

Characteristics and Generation of Household Hazardous Waste (HHW) in Semarang City Indonesia

Science.gov (United States)

Fikri, Elanda; Purwanto; Sunoko, Henna Rya

2018-02-01

Most of Household Hazardous Waste (HHW) is currently mixed with domestics waste. So that, it can impact human health and environmental quality. One important aspect in the management strategy is to determine the quantity generated and characteristics of HHW. The method used to determine the characteristics HHW refers to SNI 19-2454-2002, while the HHW generation refers to the SNI 19-3694-1994 calculated based on weight and volume. Research was conducted in four districts of Semarang. The samples used in this study were 400 families calculated based on the proportion of Slovin Formula. The characteristic of HHW in Semarang City is mainly infectious (79%), then poisonous (13%), combustible (6%) and corrosive materials (2%). The quantity HHW generated is 0.01 kg/person/day equivalent with 5.1% of municipal solid waste (MSW) in Semarang (linear equations : y=1,278x+82,00 (volume), y=0,216x+13,89 (weight).

Leaching characteristics, ecotoxicity, and risk assessment based management of mine wastes

Science.gov (United States)

Kim, J.; Ju, W. J.; Jho, E. H.; Nam, K.; Hong, J. K.

2016-12-01

Mine wastes generated during mining activities in metal mines generally contain high concentrations of metals that may impose toxic effects to surrounding environment. Thus, it is necessary to properly assess the mining-impacted landscapes for management. The study investigated leaching characteristics, potential environmental effects, and human health risk of mine wastes from three different metal mines in South Korea (molybdenum mine, lead-zinc mine, and magnetite mine). The heavy metal concentrations in the leachates obtained by using the Korean Standard Test Method for Solid Wastes (STM), Toxicity Characteristics Leaching Procedure (TCLP), and Synthetic Precipitation Leaching Procedure (SPLP) met the Korea Waste Control Act and the USEPA region 3 regulatory levels accordingly, even though the mine wastes contained high concentrations of metals. Assuming that the leachates may get into nearby water sources, the leachate toxicity was tested using Daphnia Magna. The toxic unit (TU) values after 24 h and 48 h exposure of all the mine wastes tested met the Korea Allowable Effluent Water Quality Standards (TUwaste may have long-term toxic effects (TU>1 for the eluent at L/S of 30) implying that the long-term effect of mine wastes left in mining areas need to be assessed. Considering reuse of mine wastes as a way of managing mine wastes, the human health risk assessment of reusing the lead-zinc mine waste in industrial areas was carried out using the bioavailable fraction of the heavy metals contained in the mine wastes, which was determined by using the Solubility/Bioavailability Research Consortium method. There may be potential carcinogenic risk (9.7E-05) and non-carcinogenic risk (HI, Hazard Index of 1.0E+00) as CR≧1.0E-05 has carcinogenic risk and HI≧1.0E+00 has non-carcinogenic risk. Overall, this study shows that not only the concentration-based assessment but ecological toxic effect and human health risk based assessments can be utilized for mining

Assessment of waste characteristics and waste management practices for the Midwest Compact Region: Regional Management Plan

International Nuclear Information System (INIS)

1986-01-01

This report has described how the Midwest Compact region's low-level radioactive waste characteristics were determined and has provided assessments of several key characteristics of the waste. Sources of the data used and comments on the validity and uncertainty of both the raw information and the region-wide estimates that have been generated are indicated. The contents and organization of the computerized Midwest Data Base are also presented. This data base is a resource for rational development of the Midwest Compact's Regional Management Plan. The value of the level of detail contained in Midwest Data Base is demonstrated in its use to analyze the viability of LLW treatment alternatives in other aspects of the regional management plan (RAE86). 10 refs., 7 figs., 13 tabs

Waste Management Program management plan. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-02-01

As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management`s objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL.

Integrated data base for 1990: US spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1990-10-01

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1989. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 22 refs., 48 figs., 109 tabs

Integrated Data Base for 1991: US spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1991-10-01

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1990. These data are based on the most reliable information available form government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated generally through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 160 refs., 61 figs., 142 tabs

FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

Energy Technology Data Exchange (ETDEWEB)

Templeton, K.J.

1996-05-23

For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company`s Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division`s treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on

FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

International Nuclear Information System (INIS)

Templeton, K.J.

1996-01-01

For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company's Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division's treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on

40 CFR 268.32 - Waste specific prohibitions-Soils exhibiting the toxicity characteristic for metals and...

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Waste specific prohibitions-Soils... Prohibitions on Land Disposal § 268.32 Waste specific prohibitions—Soils exhibiting the toxicity characteristic... from land disposal: any volumes of soil exhibiting the toxicity characteristic solely because of the...

Combustion and fuel loading characteristics of Hanford Site transuranic solid waste

International Nuclear Information System (INIS)

Greenhalgh, W.O.

1994-01-01

The Waste Receiving and Processing (WRAP) Facility is being designed for construction in the north end of the Central Waste Complex. The WRAP Facility will receive, store, and process radioactive solid waste of both transuranic (TRU) and mixed waste (mixed radioactive-chemical waste) categories. Most of the waste is in 208-L (55-gal) steel drums. Other containers such as wood and steel boxes, and various sized drums will also be processed in the facility. The largest volume of waste and the type addressed in this report is TRU in 208-L (55-gal) drums that is scheduled to be processed in the Waste Receiving and Processing Facility Module 1 (WRAP 1). Half of the TRU waste processed by WRAP 1 is expected to be retrieved stored waste and the other half newly generated waste. Both the stored and new waste will be processed to certify it for permanent storage in the Waste Isolation Pilot Plant (WIPP) or disposal. The stored waste will go through a process of retrieval, examination, analysis, segregation, repackaging, relabeling, and documentation before certification and WIPP shipment. Newly generated waste should be much easier to process and certify. However, a substantial number of drums of both retrievable and newly generated waste will require temporary storage and handling in WRAP. Most of the TRU waste is combustible or has combustible components. Therefore, the presence of a substantial volume of drummed combustible waste raises concern about fire safety in WRAP and similar waste drum storage facilities. This report analyzes the fire related characteristics of the expected WRAP TRU waste stream

Combustion Characteristics Of Agricultural Waste-Coal Char Blends

International Nuclear Information System (INIS)

Akpabio, I. O; Danbature W

2002-01-01

Shortage of petroleum products, depletion of huge forest reserves for fuel purposes with its attendant erosion problems and other environmental considerations have necessitated investigations into other sources of fuel. In this wise. a set of seven types of briquettes were prepared from agricultural wastes such as rice husk, maize husk and saw-dust and blends of carbonized coal char. Strong and well-formed briquettes with good combustion characteristics were obtained. The results obtained from water boiling tests show that 2 litres of water could be boiled just under 23 minutes. Moisture contents and strengths of these briquettes were also determined and are discussed. The results show that wastes could be converted into useful fuel

Nuclear waste management: a perspective

International Nuclear Information System (INIS)

Leuze, R.E.

1980-01-01

The scope of our problems with nuclear waste management is outlined. Present and future inventories of nuclear wastes are assessed for risk. A discussion of what is presently being done to solve waste management problems and what might be done in the future are presented

Mine waste disposal and managements

Energy Technology Data Exchange (ETDEWEB)

Cheong, Young Wook; Min, Jeong Sik; Kwon, Kwang Soo; Kim, Ok Hwan; Kim, In Kee; Song, Won Kyong; Lee, Hyun Joo [Korea Institute of Geology Mining and Materials, Taejon (Korea)

1998-12-01

Acid Rock Drainage (ARD) is the product formed by the atmospheric oxidation of the relatively common pyrite and pyrrhotite. Waste rock dumps and tailings containing sulfide mineral have been reported at toxic materials producing ARD. Mining in sulphide bearing rock is one of activity which may lead to generation and release of ARD. ARD has had some major detrimental affects on mining areas. The purpose of this study was carried out to develop disposal method for preventing contamination of water and soil environment by waste rocks dump and tailings, which could discharge the acid drainage with high level of metals. Scope of this study was as following: environmental impacts by mine wastes, geochemical characteristics such as metal speciation, acid potential and paste pH of mine wastes, interpretation of occurrence of ARD underneath tailings impoundment, analysis of slope stability of tailings dam etc. The following procedures were used as part of ARD evaluation and prediction to determine the nature and quantities of soluble constituents that may be washed from mine wastes under natural precipitation: analysis of water and mine wastes, Acid-Base accounting, sequential extraction technique and measurement of lime requirement etc. In addition, computer modelling was applied for interpretation of slope stability od tailings dam. (author). 44 refs., 33 tabs., 86 figs.

Experimental Studies on Combustion Characteristics of Mixed Municipal Solid Waste

Institute of Scientific and Technical Information of China (English)

Fan Jiang; Zhonggang Pan; Shi Liu; Haigang Wang

2003-01-01

In our country, municipal solid wastes (MSW) are always burnt in their original forms and only a few pretreatments are taken. Therefore it is vital to study the combustion characteristics of mixed waste. In this paper,thermogravimetric analysis and a lab scale fluidized bed facility were used as experimental means. The data in two different experimental systems were introduced and compared. It took MSW 3～3.5 rain to burn out in FB, but in thermogravimetric analyzer, the time is 20～25 min. It can be concluded that, in general, the behavior of a mixture of waste in TGA can be expressed by simple combination of individual components of the waste mixtures.Only minor deviations from the rule were observed. Yet, in Fluidized Bed, it was found that, for some mixtures,there was interference among the components during fluidized bed combustion.

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 Encapsulation and Storage Facility (WESF) Waste Analysis Plan

International Nuclear Information System (INIS)

SIMMONS, F.M.

2000-01-01

The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Waste Encapsulation and Storage Facility (WESF) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (3), (4), (5), and (6). WESF is an interim status other storage-miscellaneous storage unit. WESF stores mixed waste consisting of radioactive cesium and strontium salts. WESF is located in the 200 East Area on the Hanford Facility. 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 Evaluation on Characteristics of Waste from Pyro-processing (FS v5.1)

International Nuclear Information System (INIS)

Kim, In-Young; Choi, Heui-Joo

2016-01-01

In this study, characteristic of waste from pyro-processing which based on material balance FS v5.1 is evaluated for revising of A-KRS concept. To reduce volume and toxicity of PWR SNFs, the P and T Technology using pyro-processing and SFR is under development in KAERI. In accordance with this R and D, the A-KRS was developed by KAERI for disposal of waste from pyro-processing. After A-KRS concept development, material balance has been revised and characteristics of waste have been changed. To solve impending saturation of storage capacity of NPP sites, national policy on SNF management seems to be determined shortly. Demand on detailed analysis on impact of P and T using pyro-processing and SFR as base data is increasing. To compare direct disposal scenario to the P and T scenario using pyro-processing and SFR, updating of A-KRS reflecting amendment of material balance is required. In this study, characteristic of waste from pyro-processing which based on material balance FS v5.1 is evaluated. Every 15 types of outputs generated from pyro-processing are evaluated. Great reduction can be achieved by complete reuse of U/TRU/RE in SFR, because most of decay heat, radioactivity and radiotoxicity are generated from U/TRU/RE ingot. Within about 300 years, the fly ash filter containing Cs, Sr containing salt waste are important waste in perspective of decay heat and radioactivity. Importance of RE containing salt waste reduced. Management of hold-ups must be clarified because hold-ups take large portion of decay heat, radioactivity in the material balance FS v5.1

Preliminary Evaluation on Characteristics of Waste from Pyro-processing (FS v5.1)

Energy Technology Data Exchange (ETDEWEB)

Kim, In-Young; Choi, Heui-Joo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

In this study, characteristic of waste from pyro-processing which based on material balance FS v5.1 is evaluated for revising of A-KRS concept. To reduce volume and toxicity of PWR SNFs, the P and T Technology using pyro-processing and SFR is under development in KAERI. In accordance with this R and D, the A-KRS was developed by KAERI for disposal of waste from pyro-processing. After A-KRS concept development, material balance has been revised and characteristics of waste have been changed. To solve impending saturation of storage capacity of NPP sites, national policy on SNF management seems to be determined shortly. Demand on detailed analysis on impact of P and T using pyro-processing and SFR as base data is increasing. To compare direct disposal scenario to the P and T scenario using pyro-processing and SFR, updating of A-KRS reflecting amendment of material balance is required. In this study, characteristic of waste from pyro-processing which based on material balance FS v5.1 is evaluated. Every 15 types of outputs generated from pyro-processing are evaluated. Great reduction can be achieved by complete reuse of U/TRU/RE in SFR, because most of decay heat, radioactivity and radiotoxicity are generated from U/TRU/RE ingot. Within about 300 years, the fly ash filter containing Cs, Sr containing salt waste are important waste in perspective of decay heat and radioactivity. Importance of RE containing salt waste reduced. Management of hold-ups must be clarified because hold-ups take large portion of decay heat, radioactivity in the material balance FS v5.1.

Environmental and waste management issues, causes, characteristics, and cures

International Nuclear Information System (INIS)

Duffy, L.P.

1992-01-01

The department of Energy (DOE) views as one of its most challenging problems the minimization, management, and cleanup of waste materials generated from Departmental operations. The challenges for the DOE have striking similarities to the environmental restoration and waste management challenges associated with energy production and the mining and mineral processing industries. Their challenges relate to uranium mining and the resulting mill tailings; decontamination and decommissioning of facilities; processing of nuclear materials and production of weapons components. Add to this the challenge of environmental restoration solutions for waste disposal practices of the past. The fundamental goal of the DOE is to ensure that risks to human health and safety and to the environment posed by the department's past, present, and future operations are either eliminated to reduced to prescribed levels by the year 2019. To achieve this goal they must be able to assess environmental and health impacts resulting from the low concentrations of contaminants. This paper presents an overview of the causes, characteristics, and cures for these environmental restoration and waste management issues

Waste inventory, waste characteristics and waste repositories in Japan

International Nuclear Information System (INIS)

Shimooka, K.

1997-01-01

There are two types of repositories for the low level radioactive wastes in Japan. One is a trench type repository only for concrete debris generated from the dismantling of the research reactor. According to the safety assurance system, Japan Atomic Energy Research Institute (JAERI) has disposed of the concrete debris arose from the dismantling of the Japan Power Demonstration Reactor (JPDR). The other type is the concreted pit with engineered barriers. Rokkasho Low Level Radioactive Waste Disposal Center has this type of repository mainly for the power plant wastes. Japan Nuclear Fuel Ltd. (JNFL) established by electric power companies is the operator of the LLW disposal project. JNFL began the storage operation in 1992 and buried approximately 60,000 drums there. Two hundred thousand drums of uniformly solidified, waste may be buried ultimately. 4 refs, 3 tabs

The ground water chemical characteristics of Beishan area-the China's potential high level radioactive waste repository

International Nuclear Information System (INIS)

Yang Tianxiao; Guo Yonghai

2004-01-01

The ground water chemical characteristics have impact on nuclide migration in high level waste repository, so the study on the ground water chemical characteristics is an important aspect in site screening and characterization. The geochemical modeling of the reaction trend between ground water and solid phase, the water-rock interaction modeling of the formation and evolution of ground water chemistry, the modeling of the reaction between ground water and nuclear waste are all carried out in this paper to study the ground water chemical characteristics in Beishan area. The study illustrates that the ground water chemical characteristics in Beishan area is favorable to the disposal of high level nuclear waste and to prevent the nuclides migration. (author)

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

Viability Assessment of a Repository at Yucca Mountain. Volume 1: Introduction and Site Characteristics

Energy Technology Data Exchange (ETDEWEB)

None

1998-12-01

This first volume contains an introduction to the viability assessment, including the purpose, scope, waste forms, technical challenges, an historical perspective, regulatory framework, management of the repository, technical components, preparations for the license application, and repository milestones after the assessment. The second part of this first volume addresses characteristics of the Yucca Mountain site.

Characteristics of special-case wastes potentially destined for disposal at the Nevada Test Site

International Nuclear Information System (INIS)

Price, L.L.; Duran, F.A.

1994-09-01

The U.S. Department of Energy (DOE) is responsible for disposing of a variety of radioactive and mixed wastes, some of which are considered special-case waste because they do not currently have a clear disposal option. It may be possible to dispose of some of the DOE's special-case waste using greater confinement disposal techniques at the Nevada Test Site (NTS). The DOE asked Sandia National Laboratories to investigate this possibility by performing system configuration analyses. The first step in performing system configuration analyses is to estimate the characteristics of special-case waste that might be destined for disposal at the NTS. The objective of this report is to characterize this special-case waste based upon information available in the literature. No waste was sampled and analyzed specifically for this report. The waste compositions given are not highly detailed, consisting of grains and curies of specific radionuclides per cubic meter. However, such vague waste characterization is adequate for the purposes of the system configuration task. In some previous work done on this subject, Kudera et al. [1990] identified nine categories of special-case radioactive waste and estimated volumes and activities for these categories. It would have been difficult to develop waste compositions based on the categories proposed by Kudera et al. [1990], so we created five groups of waste on which to base the waste compositions. These groups are (1) transuranic waste, (2) fission product waste, (3) activation product waste, (4) mobile/volatile waste, and (5) sealed sources. The radionuclides within a given group share common characteristics (e.g., alpha-emitters, heat generators), and we believe that these groups adequately represent the DOE's special-case waste potentially destined for greater confinement disposal at the NTS

Evaluation of thermal hydraulics characteristics of natural cooling low level radioactive waste storage system

International Nuclear Information System (INIS)

Yoshii, Toshihiro; Iwaki, Chikako; Ikeda, Tatsumi; Ikeda, Hiroshi; Koyama, Tomonori; Usui, Nobuhiko; Watanabe, Hisao; Masaki, Yoshikazu

2012-01-01

It is necessary to design a low level radioactive waste storage system so that the decay heat of radioactive waste does not breach the structural safety limit. Currently, this waste storage system is designed as a natural cooling system, which continuously cools the radioactive waste without an active device. It consists simply of a storage pit for radioactive waste and air inlet and outlet ducts. The radioactive waste is cooled by natural convective air flow, which is generated by the buoyancy of heated air due to the decay heat of radioactive waste. It is important to clarify the flow characteristics in the systems in order to evaluate the cooling performance. The air mass flow rate through the system is determined by the balance between the natural convective flow force and pressure loss within the system. Therefore, the pressure drop and flow pattern in the waste storage pit are important flow characteristics. In this study, the pressure drop and air temperature distribution, greatly influenced by the flow pattern in the pit, were measured using a 1/5 scale model and compared with the results obtained from CFD. Flow network analysis, which is a simple model that simulates the flow by nodes and junctions, was conducted and its validity was confirmed by experimental results and CFD. (author)

Characteristics of waste forms improved by using admixtures

International Nuclear Information System (INIS)

Rzyski, B.M.; Suarez, A.A.

1989-06-01

The immobilization of nitric waste streams with ordinary Portland cement can be improved by use of some admixtures. The aim of this work was to investigated how the main characteristics of waste forms prepared with Portalnd cement pastes are modified by the addition of sulphonic naphtalene acids, lignosulphonic acids and emulsified fatty acids, which are present in some commercial admixtures. The effectiveness of the admixture in reducing the pore volume, as well as improving other parameters, depends on its chemical composition and on the amount utilized as well as the water to cement ratio and salt content. The admixture which has emulsified fatty acids in its composition shows some adverse results when the samples are immersed in water. The mechanical strenght however is some what increased even when water load is increased. (author) [pt

Characteristics of waste forms improved by using admixtures

International Nuclear Information System (INIS)

Rzyski, B.M.; Suarez, A.A.

1989-01-01

The immobilization of nitric waste streams with ordinary Portland cement can be improved by use of some admixtures. The aim of this work was to investigate how the main characteristics of waste forms prepared with Portland cement pastes are modified by the addition of sulphonic naphyhalene acids, lignosulphonic acids and emulsified fatty acids, which are present in some commercial admixtures. The effectiveness of the admixtures in reducing the pore volume, as well as improving other parameters, depends on its chemical composition and on the amount utilized as well as the water to cement ratio and salt content. The admixture which has emulsified fatty acids in its composition shows some adverse results when the samples are immersed in water. The mechanical strength however is somewhat increased even when water load is increased

Integrated Data Base for 1992: US spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1992-10-01

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1991. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal

Utilization of the national Portland cement for immobilizing radioactive wastes - Physical characteristics

International Nuclear Information System (INIS)

Rzyski, B.M.; Suarez, A.A.

1988-01-01

This paper shows the results obtained in the study of the national Portland cement, P320, as matrix for radioactive nitric waste incorporation. Cement use practice in other countries is common for this purposes and demonstrates to be cheap and accessible when low and medium level wastes are immobilized. Some of physical characteristics as: homogeneity,mechanical strenght, setting and porosity are analysed due to water-cement ratio and salt contents. Those characteristics which are proper of the final product, must be controlled in such way to assure a long time integrity of the wasteform. The establishment of process and quality control criteria are based in such kind of data. (author) [pt

Solid Waste Management Program Plan

Energy Technology Data Exchange (ETDEWEB)

Duncan, D.R.

1990-08-01

The objective of the Solid Waste Management Program Plan (SWMPP) is to provide a summary level comprehensive approach for the storage, treatment, and disposal of current and future solid waste received at the Hanford Site (from onsite and offsite generators) in a manner compliant with current and evolving regulations and orders (federal, state, and Westinghouse Hanford Company (Westinghouse Hanford)). The Plan also presents activities required for disposal of selected wastes currently in retrievable storage. The SWMPP provides a central focus for the description and control of cost, scope, and schedule of Hanford Site solid waste activities, and provides a vehicle for ready communication of the scope of those activities to onsite and offsite organizations. This Plan represents the most complete description available of Hanford Site Solid Waste Management (SWM) activities and the interfaces between those activities. It will be updated annually to reflect changes in plans due to evolving regulatory requirements and/or the SWM mission. 8 refs., 9 figs., 4 tabs.

Evaluation of site-generated radioactive waste treatment and disposal methods for the Yucca Mountain repository

International Nuclear Information System (INIS)

Subramanian, C.V.; Jardine, L.J.

1989-01-01

This study identifies the sources of radioactive wastes that may be generated at the proposed high-level waste (HLW) repository at Yucca Mountain, NV, estimates the waste quantities and characteristics, compares technologies available for waste treatment and disposal, and develops recommended concepts for site-generated waste treatment and disposal. The scope of this study is limited to operations during the emplacement phase, in which 70,000 MTU of high-level waste will be received and emplaced at the proposed repository. The evaluations consider all radioactive wastes generated during normal operations in surface and underground facilities. Wastes generated as a result of accidents are not addressed; accidents that could result in large quantities of radioactive waste are expected to occur very infrequently and temporary, portable systems could be used for any necessary cleanup. The results of this study can be used to develop more definitive plans for managing the site-generated wastes and as a basis for the design of associated facilities at the proposed repository

Waste Package Lifting Calculation

International Nuclear Information System (INIS)

H. Marr

2000-01-01

The objective of this calculation is to evaluate the structural response of the waste package during the horizontal and vertical lifting operations in order to support the waste package lifting feature design. The scope of this calculation includes the evaluation of the 21 PWR UCF (pressurized water reactor uncanistered fuel) waste package, naval waste package, 5 DHLW/DOE SNF (defense high-level waste/Department of Energy spent nuclear fuel)--short waste package, and 44 BWR (boiling water reactor) UCF waste package. Procedure AP-3.12Q, Revision 0, ICN 0, calculations, is used to develop and document this calculation

Characteristics of solidified products containing radioactive molten salt waste.

Science.gov (United States)

Park, Hwan-Seo; Kim, In-Tae; Cho, Yong-Zun; Eun, Hee-Chul; Kim, Joon-Hyung

2007-11-01

The molten salt waste from a pyroprocess to recover uranium and transuranic elements is one of the problematic radioactive wastes to be solidified into a durable wasteform for its final disposal. By using a novel method, named as the GRSS (gel-route stabilization/solidification) method, a molten salt waste was treated to produce a unique wasteform. A borosilicate glass as a chemical binder dissolves the silicate compounds in the gel products to produce one amorphous phase while most of the phosphates are encapsulated by the vitrified phase. Also, Cs in the gel product is preferentially situated in the silicate phase, and it is vitrified into a glassy phase after a heat treatment. The Sr-containing phase is mainly phosphate compounds and encapsulated by the glassy phase. These phenomena could be identified by the static and dynamic leaching test that revealed a high leach resistance of radionuclides. The leach rates were about 10(-3) - 10(-2) g/m2 x day for Cs and 10(-4) - 10(-3) g/m2 x day for Sr, and the leached fractions of them were predicted to be 0.89% and 0.39% at 900 days, respectively. This paper describes the characteristics of a unique wasteform containing a molten salt waste and provides important information on a newly developed immobilization technology for salt wastes, the GRSS method.

Integrated data base for 1986: spent fuel and radioactive waste inventories, projections, and characteristics. Revision 2

International Nuclear Information System (INIS)

1986-09-01

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US Department of Energy (DOE) radioactive wastes through December 31, 1985, based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. Current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the expected defense-related and private industrial and institutional activities and the latest DOE/Energy Information Administration (EIA) projections of US commercial nuclear power growth. The materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or calculated isotopic compositions

SCOPE, Shipping Cask Optimization and Parametric Evaluation

International Nuclear Information System (INIS)

2002-01-01

1 - Description of program or function: Given the neutron and gamma-ray shielding requirements as input, SCOPE may be used as a conceptual design tool for the evaluation of various casks designed to carry square fuel assemblies, circular canisters of nuclear waste material, or circular canisters containing 'intact' spent-fuel assemblies. It may be used to evaluate a specific design or to search for the maximum number of full assemblies (or canisters) that might be shipped in a given type of cask. In the 'search' mode, SCOPE will use built-in packing arrangements and the tabulated shielding requirements input by the user to 'design' a cask carrying one fuel assembly (or canister); it will then continue to increment the number of assemblies (or canisters) until one or more of the design limits can no longer be met. In each case (N = 1,2,3...), SCOPE will calculate the steady-state temperature distribution throughout the cask and perform a complete 1-D space/time transient thermal analysis following a postulated half-hour fire; then it will edit the characteristic dimensions of the cask (including fins, if required), the total weight of the loaded case, the steady-state temperature distribution at selected points, and the maximum transient temperature in key components. With SCOPE, the effects of various design changes may be evaluated quickly and inexpensively. 2 - Method of solution: SCOPE assumes that the user has already made an independent determination of the neutron and gamma-ray shielding requirements for the particular type of cask(s) under study. The amount of shielding required obviously depends on the type of spent fuel or nuclear waste material, its burnup and/or exposure, the decay time, and the number of assemblies or canisters in the cask. Source terms (and spectra) for spent PWR and BWR fuel assemblies are provided at each of 17 decay times, along with recommended neutron and gamma-ray shield thicknesses for Pb, Fe, and U-metal casks containing a

Remote-handled transuranic waste study

International Nuclear Information System (INIS)

1995-10-01

The Waste Isolation Pilot Plant (WIPP) was developed by the US Department of Energy (DOE) as a research and development facility to demonstrate the safe disposal of transuranic (TRU) radioactive wastes generated from the Nation's defense activities. The WIPP disposal inventory will include up to 250,000 cubic feet of TRU wastes classified as remote handled (RH). The remaining inventory will include contact-handled (CH) TRU wastes, which characteristically have less specific activity (radioactivity per unit volume) than the RH-TRU wastes. The WIPP Land Withdrawal Act (LWA), Public Law 102-579, requires a study of the effect of RH-TRU waste on long-term performance. This RH-TRU Waste Study has been conducted to satisfy the requirements defined by the LWA and is considered by the DOE to be a prudent exercise in the compliance certification process of the WIPP repository. The objectives of this study include: conducting an evaluation of the impacts of RH-TRU wastes on the performance assessment (PA) of the repository to determine the effects of Rh-TRU waste as a part of the total WIPP disposal inventory; and conducting a comparison of CH-TRU and RH-TRU wastes to assess the differences and similarities for such issues as gas generation, flammability and explosiveness, solubility, and brine and geochemical interactions. This study was conducted using the data, models, computer codes, and information generated in support of long-term compliance programs, including the WIPP PA. The study is limited in scope to post-closure repository performance and includes an analysis of the issues associated with RH-TRU wastes subsequent to emplacement of these wastes at WIPP in consideration of the current baseline design. 41 refs

The development of hazardous waste management as a state policy concern

International Nuclear Information System (INIS)

Herzik, E.B.

1992-01-01

Hazardous waste management has become a primary concern of state governments. This concern is relatively recent, with state governments assuming a leading role in hazardous waste policy development and implementation only in the past decade. This article outlines the scope of the hazardous waste problem to which state governments must respond. The scope of the problem is then linked to changing public perceptions and intergovernmental relationships to explain the expanding state government policy role in hazardous waste management. 15 refs., 1 tab

Interface control document between Analytical Services and Solid Waste Disposal Division

International Nuclear Information System (INIS)

Venetz, T.J.

1995-01-01

This interface control document (ICD) between Analytical Services and Solid Waste Disposal (SWD) establishes a baseline description of the support needed and the wastes that will require management as part of the interface between the two divisions. It is important that each division has a clear understanding of the other division's expectations regarding levels and type of support needed. This ICD deals with the waste sampling support needed by SWD and the waste generated by the specified analytical laboratories. The baseline description of wastes includes waste volumes, characteristics and shipping schedules, which will be used to plan the proper support requirements. The laboratories included in this document are 222-S Laboratory Facility, the Waste Sampling and Characterization Facility (WSCF) and the Chemical Engineering Laboratory. These three facilities provide support to the entire site and are not associated with one major program/facility. The laboratories associated with major facilities or programs such as Engineering/Environmental Development Laboratory at K Basins Operation are not within the scope of this document

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

Identification of influencing municipal characteristics regarding household waste generation and their forecasting ability in Biscay

Energy Technology Data Exchange (ETDEWEB)

Oribe-Garcia, Iraia, E-mail: iraia.oribe@deusto.es; Kamara-Esteban, Oihane; Martin, Cristina; Macarulla-Arenaza, Ana M.; Alonso-Vicario, Ainhoa

2015-05-15

Highlights: • We have modelled household waste generation in Biscay municipalities. • We have identified relevant characteristics regarding household waste generation. • Factor models are used in order to identify the best subset of explicative variables. • Biscay’s municipalities are grouped by means of hierarchical clustering. - Abstract: The planning of waste management strategies needs tools to support decisions at all stages of the process. Accurate quantification of the waste to be generated is essential for both the daily management (short-term) and proper design of facilities (long-term). Designing without rigorous knowledge may have serious economic and environmental consequences. The present works aims at identifying relevant socio-economic features of municipalities regarding Household Waste (HW) generation by means of factor models. Factor models face two main drawbacks, data collection and identifying relevant explanatory variables within a heterogeneous group. Grouping similar characteristics observations within a group may favour the deduction of more robust models. The methodology followed has been tested with Biscay Province because it stands out for having very different municipalities ranging from very rural to urban ones. Two main models are developed, one for the overall province and a second one after clustering the municipalities. The results prove that relating municipalities with specific characteristics, improves the results in a very heterogeneous situation. The methodology has identified urban morphology, tourism activity, level of education and economic situation as the most influencing characteristics in HW generation.

Identification of influencing municipal characteristics regarding household waste generation and their forecasting ability in Biscay

International Nuclear Information System (INIS)

Oribe-Garcia, Iraia; Kamara-Esteban, Oihane; Martin, Cristina; Macarulla-Arenaza, Ana M.; Alonso-Vicario, Ainhoa

2015-01-01

Highlights: • We have modelled household waste generation in Biscay municipalities. • We have identified relevant characteristics regarding household waste generation. • Factor models are used in order to identify the best subset of explicative variables. • Biscay’s municipalities are grouped by means of hierarchical clustering. - Abstract: The planning of waste management strategies needs tools to support decisions at all stages of the process. Accurate quantification of the waste to be generated is essential for both the daily management (short-term) and proper design of facilities (long-term). Designing without rigorous knowledge may have serious economic and environmental consequences. The present works aims at identifying relevant socio-economic features of municipalities regarding Household Waste (HW) generation by means of factor models. Factor models face two main drawbacks, data collection and identifying relevant explanatory variables within a heterogeneous group. Grouping similar characteristics observations within a group may favour the deduction of more robust models. The methodology followed has been tested with Biscay Province because it stands out for having very different municipalities ranging from very rural to urban ones. Two main models are developed, one for the overall province and a second one after clustering the municipalities. The results prove that relating municipalities with specific characteristics, improves the results in a very heterogeneous situation. The methodology has identified urban morphology, tourism activity, level of education and economic situation as the most influencing characteristics in HW generation

Factors that influence public awareness of domestic waste characteristics and management in rural areas.

Science.gov (United States)

Han, Zhiyong; Duan, Qingqing; Fei, Yongqiang; Zeng, Dan; Shi, Guozhong; Li, Haimei; Hu, Meilun

2018-05-01

Public awareness of domestic waste characteristics and management (PADWCM) is a prerequisite for a domestic waste management (DWM) plan. In this study, we considered China as a typical example of developing countries to investigate the public perception of environmental pollution (PEP), its PADWCM, and its socioeconomic factors, using questionnaires and statistical methods. The results indicated that the public PEP was mainly due to obvious environmental contamination in local villages, and the PADWCM is still inadequate in rural areas. However, 83.9% of the respondents agreed that DWM is highly necessary. The PADWCM, including the hazard, recyclability, and characteristic pollution caused by domestic waste, was learned mainly from people's direct PEP, experiences, and repurchasing by recyclers. Education period had highly significant positive correlations and regressions with PEP and PADWCM, respectively. Additionally, education directly affected public awareness in different income and age groups. Demonstration projects had a significant positive effect on the awareness of characteristic pollution caused by domestic waste, which was readily perceived. Propaganda had a significant positive influence on the awareness of treatment necessity. Age and gender had no obvious effects on public PEP and PADWCM. Some aspects of PADWCM requiring a deep understanding became stronger as income increased; however, the PADWCM located close to poor people became weaker. Some aspects of PEP could significantly influence the awareness of characteristic pollution caused by domestic waste and awareness of treatment necessity. Therefore, improving environmental education, performing demonstration projects and effective environmental propaganda, increasing people's income, and attracting young people to participate in DWM will be important for enhancing environmental awareness and DWM in rural areas. Integr Environ Assess Manag 2018;14:395-406. © 2018 SETAC. © 2018 SETAC.

40 CFR 262.10 - Purpose, scope, and applicability.

Science.gov (United States)

2010-07-01

... (CONTINUED) STANDARDS APPLICABLE TO GENERATORS OF HAZARDOUS WASTE General § 262.10 Purpose, scope, and..., Geology, Physics, Psychology Merkert Chemistry Building, 2609 Beacon St., Boston, MA, Higgins Building..., Biology, Psychology, Anthropology, Geology and Earth Sciences, and Environmental, Coastal and Ocean...

Characteristics of fuel cycle waste

International Nuclear Information System (INIS)

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

1982-01-01

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

Analysis of space systems for the space disposal of nuclear waste follow-on study. Volume 2: Technical report

Science.gov (United States)

1982-01-01

The space option for disposal of certain high-level nuclear wastes in space as a complement to mined geological repositories is studied. A brief overview of the study background, scope, objective, guidelines and assumptions, and contents is presented. The determination of the effects of variations in the waste mix on the space systems concept to allow determination of the space systems effect on total system risk benefits when used as a complement to the DOE reference mined geological repository is studied. The waste payload system, launch site, launch system, and orbit transfer system are all addressed. Rescue mission requirements are studied. The characteristics of waste forms suitable for space disposal are identified. Trajectories and performance requirements are discussed.

Uncertainty characteristics of EPA's ground-water transport model for low-level waste performance assessment

International Nuclear Information System (INIS)

Yim, Man-Sung

1995-01-01

Performance assessment is an essential step either in design or in licensing processes to ensure the safety of any proposed radioactive waste disposal facilities. Since performance assessment requires the use of computer codes, understanding the characteristics of computer models used and the uncertainties of the estimated results is important. The PRESTO-EPA code, which was the basis of the Environmental Protection Agency's analysis for low-level-waste rulemaking, is widely used for various performance assessment activities in the country with no adequate information available for the uncertainty characteristics of the results. In this study, the groundwater transport model PRESTO-EPA was examined based on the analysis of 14 C transport along with the investigation of uncertainty characteristics

Development of thermal conditioning technology for alpha-contaminated wastes: a study on leaching characteristics and long-term safety assessment of simulated waste forms

Energy Technology Data Exchange (ETDEWEB)

Seo, Yong Chil [Yonsei University, Seoul (Korea); Lee, Sang Hoon; Yoo, Jong Ik; Choi, Yong Cheol [Yonsei University, Seoul (Korea)

2001-04-01

Radioactive wastes should be stabilized for safe management during several hundred years. To assess stability of solidified waste forms, mechanical properties and chemical durability of the waste forms should be analyzed. Chemical durability is one of the most important factors in the assessment of waste forms, which could be examined by leaching tests. Various methods in leaching test are suggested by different organizations, but a formal test method in Korea is not ready yet. Therefore, the leaching test method applicable to various constituents is necessary for the safe management of radioactive wastes In this study, leaching behavior and characteristics of components such as solidification materials, heavy metals and radioactive nuclids were analyzed for cement waste form and glassy waste form. 58 refs., 25 figs., 8 tabs. (Author)

Integrated data base for 1993: US spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

Klein, J.A.; Storch, S.N.; Ashline, R.C.

1994-03-01

The Integrated Data Base (IDB) Program has compiled historic data on inventories and characteristics of both commercial and DOE spent fuel; also, commercial and U.S. government-owned radioactive wastes through December 31, 1992. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest U.S. Department of Energy/Energy Information Administration (DOE/EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste (HLW), transuranic (TRU), waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) LLW. For most of these categories, current and projected inventories are given through the calendar-year (CY) 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal

A study on the establishment of the regulatory guide to the characteristics and classification criteria of low and intermediate level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Lee, Geon Jae; Paek, Min Hoon; Park, Jong Gil; Han, Byeong Seop; Cheong, Jae Hak; Lee, Hae Chan; Yang, Jin Yeong; Hong, Hei Kwan; Park, Jin Baek [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1995-01-15

The objectives of this study are the development of regulatory guidance to the establishment of the necessary technology standard of the characteristics and classification criteria of low and intermediate level radioactive waste for the safe operation of the waste repositories. In followings, the contents of our report will be presented in two parts. Survey of the characteristics of radioactive waste : investigate and analyze the source, types and characteristics of domestic radioactive waste as a basis for this study, radiochemical analysis of radioactive waste based on foreign and domestic data base, determination of the methodology for the application of the characteristic analysis of waste classification technology. Establishment of the classification criteria of the radioactive waste : collection and analysis of foreign and domestic data base on the classification methodology and criteria, development of low and intermediate level waste classification criteria and the set up of the classification methodology through the analysis of waste data, establishment of the systematic classification methodology of the low and intermediate radioactive waste through the careful survey of the current domestic regulation.

Characteristics of waste automotive glasses as silica resource in ferrosilicon synthesis.

Science.gov (United States)

Farzana, Rifat; Rajarao, Ravindra; Sahajwalla, Veena

2016-02-01

This fundamental research on end-of-life automotive glasses, which are difficult to recycle, is aimed at understanding the chemical and physical characteristics of waste glasses as a resource of silica to produce ferrosilicon. Laboratory experiments at 1550°C were carried out using different automotive glasses and the results compared with those obtained with pure silica. In situ images of slag-metal separation showed similar behaviour for waste glasses and silica-bearing pellets. Though X-ray diffraction (XRD) showed different slag compositions for glass and silica-bearing pellets, formation of ferrosilicon was confirmed. Synthesized ferrosilicon alloy from waste glasses and silica were compared by Raman, X-ray photoelectron spectroscopy and scanning electron microscopy (SEM) analysis. Silicon concentration in the synthesized alloys showed almost 92% silicon recovery from the silica-bearing pellet and 74-92% silicon recoveries from various waste glass pellets. The polyvinyl butyral (PVB) plastic layer in the windshield glass decomposed at low temperature and did not show any detrimental effect on ferrosilicon synthesis. This innovative approach of using waste automotive glasses as a silica source for ferrosilicon production has the potential to create sustainable pathways, which will reduce specialty glass waste in landfill. © The Author(s) 2015.

Characteristics of Indigenous primary health care models of service delivery: a scoping review protocol.

Science.gov (United States)

Harfield, Stephen; Davy, Carol; Kite, Elaine; McArthur, Alexa; Munn, Zachary; Brown, Ngiare; Brown, Alex

2015-11-01

The objective of the scoping review is to identify and describe within the existing literature the characteristics (values, principles, components and suggest practical applications) of primary health care models of service delivery for Indigenous people. More specifically, the review question is:What are the characteristics (values, principles, components and suggested practical applications) of primary health care models of service delivery for Indigenous people?Findings from this scoping review will inform two systematic reviews. One of these will explore the acceptability and the other the effectiveness of identified characteristics. The scoping review will follow the JBI Scoping Review methodology as outlined in the 2015 Joanna Briggs Institute Reviewers' Manual. Indigenous populations in colonized countries experience worse health outcomes relative to their non-Indigenous counterparts. In Australia, in the period 2010 to 2012 the estimated gap in life expectancy between Aboriginal and Torres Strait Islander Australians compared to non-Indigenous Australians was 10 years Similar gaps in life expectancy between Indigenous and non-Indigenous have been demonstrated in other countries, such as New Zealand, Canada and the United StatesThe gap in life expectancy and the health disadvantage experienced by Indigenous people is in part the result of mainstream health services not adequately meeting the health needs of Indigenous people and Indigenous people's inability to access mainstream services Part of the solution has been the establishment of primary health care services for and in many cases run by Indigenous people. Indigenous primary health services have been developed to provide culturally appropriate services that meet the needs of local Indigenous communities.In Australia, the first Aboriginal medical service was established in 1971 in Redfern, New South Wales, by "community activists in response to ongoing discrimination against Aboriginal people within

Safe Management of Waste Generated during Shale Gas Operations

Science.gov (United States)

Kukulska-Zając, Ewa; Król, Anna; Holewa-Rataj, Jadwiga

2017-04-01

Exploration and exploitation of hydrocarbon deposits, regardless of their type, are connected with the generation of waste, which may have various environmental effects. Such wastes may pose a serious risk to the surrounding environment and public health because they usually contain numerous potentially toxic chemicals. Waste associated with exploration and exploitation of unconventional hydrocarbon deposits is composed of a mixture of organic and inorganic materials, the qualitative and quantitative composition of which changes widely over time, depending on numerous factors. As a result the proper characteristic of this type of waste is very important. Information gained from detailed chemical analyses of drilling chemicals, drilling wastes, and flowback water can be used to manage shale gas-related wastes more appropriately, to develop treatment methods, to store the waste, and assess the potential environmental and health risk. The following paper will focus mainly on the results of research carried out on waste samples coming from the unconventional hydrogen exploration sites. Additionally, regulatory frameworks applicable to the management of wastes produced during this type of works will be discussed. The scope of research concerning physicochemical parameters for this type of wastes will also be presented. The presented results were obtained during M4ShaleGas project realization. The M4ShaleGas project has received funding from the European Union's Horizon 2020 research and innovation programme under grant agreement no. 640715.

Quantities and characteristics of the contact-handled low-level mixed waste streams for the DOE complex

International Nuclear Information System (INIS)

Huebner, T.L.; Wilson, J.M.; Ruhter, A.H.; Bonney, S.J.

1994-08-01

This report supports the Integrated Thermal Treatment System (ITTS) Study initiated by the Department of Energy (DOE) Office of Technology Development (EM-50), which is a system engineering assessment of a variety of mixed waste treatment process. The DOE generates and stores large quantities of mixed wastes that are contaminated with both chemically hazardous and radioactive species. The treatment of these mixed wastes requires meeting the standards established by the Environmental Protection Agency for the specific hazardous contaminants regulated under the Resource Conservation and Recovery Act while also providing adequate control of the radionuclides. The thrust of the study is to develop preconceptual designs and life-cycle cost estimates for integrated thermal treatment systems ranging from conventional incinerators, such as rotary kiln and controlled air systems, to more innovative but not yet established technologies, such as molten salt and molten metal waste destruction systems. Prior to this engineering activity, the physical and chemical characteristics of the DOE low-level mixed waste streams to be treated must be defined or estimated. This report describes efforts to estimate the DOE waste stream characteristics

Safety characteristics of potential waste transmutation systems

International Nuclear Information System (INIS)

Van Tuyle, G.J.

1993-01-01

For nuclear waste transmutation to alter significantly the need for geologic disposal of spent fuel from US Light-water reactors (LWRs), about 1.4% of the spent fuel (by mass) must be separated and transmuted. This includes the plutonium, the minor actinides, and four fission products: iodine. technetium, cesium and strontium. Regarding the actinides, fissioning of the plutonium, neptunium, americium, and curium generates a great deal of heat, so much so that most of the plutonium should be used to produce power. However, these actinides have some undesirable neutronic characteristics, and their utilization in reactors or subcritical (proton-accelerator) targets requires either a fast neutronic spectrum or a very high thermal-neutron flux. Transmutation of the fission products is generally by neutron capture, although this is difficult in the case of cesium and strontium. In this paper, various proposed means of transmuting the actinides and fission products are discussed, with the main focus being on the safety characteristics of each approach

Scope of Nursing Practice in a Tertiary Pediatric Setting: Associations With Nurse and Job Characteristics and Job Satisfaction.

Science.gov (United States)

Déry, Johanne; Clarke, Sean P; D'Amour, Danielle; Blais, Régis

2018-01-01

While professional nursing, like other health professions, has a recognized educational base and a legal scope of practice that is remarkably consistent across societies, there are important variations even within the same institution or organization in the extent to which professional nurses engage in the full range of activities for which they are qualified. There has been limited study of enacted (actual) scope of nursing practice (ESOP) or of its impacts on nurse job outcomes, such as job satisfaction. The aim of this study is to measure ESOP, as well as its predictors and impact on job satisfaction, in a specialty university-affiliated tertiary referral center in one of the few remaining jurisdictions outside the United States that continue to educate registered nurses at multiple educational levels. This was a correlational cross-sectional design using structural equation modeling. Self-administered questionnaires were completed by 301 registered nurses holding permanent positions in specific clinical areas for 6 months or longer in a pediatric hospital in the province of Quebec, Canada. ESOP or actual scope of practice was low-on average, nurses applied the range of skills within their theoretical scopes of practice only occasionally or "less than frequently" in their daily work (3.21 out of a possible 6 points). ESOP was strongly related to decision latitude (β = 0.319; p  = .012), role ambiguity (β = 0.297; p  = .011), and role overload (β  =  0.201; p  = .012). The personal characteristics that exerted the greatest direct influence on ESOP were education level (β  =  0.128; p  = .015) and growth need strength (β  =  0.151; p  = .008). Results also showed that ESOP exerts a direct positive influence on nurses' job satisfaction (β  =  0.118; p  = .006). Structural equation modeling analyses revealed a good fit of the data to the hypothesized conceptual model (χ²/df ratio index =  1.68, root mean square error of approximation  =  0

Secondary waste characteristics and ITS filtration system on laser cutting

Energy Technology Data Exchange (ETDEWEB)

Hara, Kunio; Miyao, Hidehiko [Research Association for Facility Decommissioning (RANDEC), Tokai, Ibaraki (Japan); Nakazawa, Masaharu [Tokyo Univ. (Japan); Kataoka, Shinichi; Nagura, Yasumi; Saiki, Hideo [Mitsubishi Heavy Industries Ltd., Tokyo (Japan)

2001-03-01

Technology of dismantling nuclear facilities has been developing in various fields for its evaluation and dismantling system. RANDEC has been studying remote dismantling system for highly activated equipments such as core internals with a laser using optical fiber. Recently a high power YAG laser having the advantage of application for remote dismantling on thick metallic material is the stage for practical use, and narrow kerf can bring the reduction of secondary waste as well. The present paper describes the experimental results and discussion on the laser cutting, including the secondary waste characteristics and its filtration system using the YAG laser. This study has been performed on consignment to RANDEC from the Science and Technology Agency of Japan. (author)

Physico-chemical characterisation of material fractions in household waste

DEFF Research Database (Denmark)

Götze, Ramona; Boldrin, Alessio; Scheutz, Charlotte

2016-01-01

State-of-the-art environmental assessment of waste management systems rely on data for the physico-chemical composition of individual material fractions comprising the waste in question. To derive the necessary inventory data for different scopes and systems, literature data from different sources...... and backgrounds are consulted and combined. This study provides an overview of physico-chemical waste characterisation data for individual waste material fractions available in literature and thereby aims to support the selection of data fitting to a specific scope and the selection of uncertainty ranges related...... to the data selection from literature. Overall, 97 publications were reviewed with respect to employed characterisation method, regional origin of the waste, number of investigated parameters and material fractions and other qualitative aspects. Descriptive statistical analysis of the reported physico...

Study on the spray characteristics of methyl esters from waste cooking oil at elevated temperature

Energy Technology Data Exchange (ETDEWEB)

Lin, Yung-Sung [Department of Mechanical and Automation Engineering, Da-Yeh University, 168 University Road, Dacun, Changhua 51591 (China); Department of Mechanical Engineering, Hsiuping Institute of Technology, No.11, Gongye Rd., Dali City, Taichung County 412-80 (China); Lin, Hai-Ping [Department of Mechanical and Automation Engineering, Da-Yeh University, 168 University Road, Dacun, Changhua 51591 (China)

2010-09-15

In Taiwan, millions of tons of waste cooking oil are produced each year, and less than 20% of it, about 150,000 ton/a, is reclaimed and reused. Most waste oil is flushed down the drain. Utilizing waste cooking oil to make biodiesel not only reduces engine exhaust gas pollution, but also replaces food-derived fuels, and reduces ecologic river pollution. This study employed two-stage transesterification to lower the high viscosity of waste oil, utilized emulsion to reduce the methyl ester NOx pollution, and used methanol to enhance the stability and viscosity of emulsified fuel. To further analyze spray characteristics of fuels, this experiment built a constant volume bomb under high temperature, used high speed photography to analyze spray tip penetration, spray angle, and the Sauter mean diameter (SMD) of fuel droplets, and compared the results with fossil diesel. The experimental results suggested that, two-stage transesterification can significantly lower waste oil viscosity to that which is close to fossil diesel viscosity. At a temperature above 300 C, waste cooking oil methyl esters had a water content of 20%, spray droplet characteristics were significantly improved, and NOx emission dropped significantly. The optimal fuel ratio suggested in this experiment was waste cooking oil methyl ester 74.5%, methanol 5%, water 20%, and composite surfactant Span-Tween 0.5%. (author)

Radiological waste problems

International Nuclear Information System (INIS)

Milanov, M.

1990-01-01

The chapter offers a description of the system of radioactive waste treatment as presented in the Belene NPP technical project and goes beyond the scope of the project evaluation in the account of the radioactive waste treatment, storage and disposal of other sources including the industry, science and the medicine of Bulgaria. The necessity for a developed legislative basis and an accepted policy regarding the radioactive waste management in the country is stressed upon. There is an elaboration on the problem of the construction of a new radioactive waste depository, the capacities of the existing disposal site being used up. 17 refs., 7 tabs. (R.Ts.)

Integrated Data Base for 1992: US spent fuel and radioactive waste inventories, projections, and characteristics. Revision 8

Energy Technology Data Exchange (ETDEWEB)

Payton, M. L.; Williams, J. T.; Tolbert-Smith, M.; Klein, J. A.

1992-10-01

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1991. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal.

Waste feed delivery test and evaluation plan

Energy Technology Data Exchange (ETDEWEB)

O' TOOLE, S.M.

1999-09-30

This plan documents the Waste Feed Delivery Program test and evaluation planning and implementation approach. The purpose of this document is to define and communicate the Waste Feed Delivery Program Test and Evaluation scope, objectives, planning and implementation approach.

Waste feed delivery test and evaluation plan

International Nuclear Information System (INIS)

O'TOOLE, S.M.

1999-01-01

This plan documents the Waste Feed Delivery Program test and evaluation planning and implementation approach. The purpose of this document is to define and communicate the Waste Feed Delivery Program Test and Evaluation scope, objectives, planning and implementation approach

Klipperaas study site. Scope of activities and main results

International Nuclear Information System (INIS)

Ahlbom, K.; Andersson, J.E.; Andersson, Peter; Ittner, T.; Tiren, S.; Ljunggren, C.

1992-09-01

During the period from 1977 - 1986 SKB (Swedish Nuclear Fuel and Waste Management Co.) performed surface and borehole investigations of 14 study sites for the purpose of assessing their suitability for a repository of spent nuclear fuel. The next phase in the SKB site selection rpogramme will be to perform detailed characterisation, including characterization from shafts and/or tunnels, of two or three sites. The detailed investigations will continue over several years to provide all the data needed for a licensing application to build a repository. Such an application is foreseen to be given to the authorities around the year 2003. It is presently not clear if any of the study sites will be selected as a site for detailed characterization. Other sites with geological and/or socio-economical characteristics judged more favorable may very well be the ones selected. However, as a part of the background documentation needed for the site selection studies to come, summary reports will be prepared for most study sites. These reports will include scope of activities, main results, uncertainties and need of complementary investigations. This report concern the Klipperaas study site. The main topics are the scope of activities, geologic model, geohydrological model, groundwater chemistry, assessment of solute transport, and rock mechanics

The characteristics of palm oil plantation solid biomass wastes as raw material for bio oil

Science.gov (United States)

Yanti, RN; Hambali, E.; Pari, G.; Suryani, A.

2018-03-01

Indonesia is the largest palm oil plantations estate in the world. It reached 11,30 million hectares in 2015 and increased up to 11,67 million hectares in 2016. The advancement of technology recent, the solid waste of palm oil plantation can be re-produced become bio oil through pyrolysis hydrothermal process and utilized for biofuel. The purpose of this research was to analyze the characteristics of feedstock of bio oil of solid waste of palm oil plantations estate. The feedstock used was derived from solid waste of palm oil plantations in Riau Province. Characteristic analysis of waste oil included chemical compound content (cellulose, hemicellulose, lignin), ultimate analysis (C, H, N, O, S) to know height heating value (HHV). The result of analysis of chemical content showed that solid waste of palm cellulose 31,33 – 66,36 %, hemicellulose 7,54 – 17,94 %, lignin 21,43 - 43,1. The HHV of hydrothermal pyrolysis feedstock was 15,18 kJ/gram - 19,57 kJ/gram. Generally, the solid waste of palm oil plantations estate containing lignocellulose can be utilized as bio oil through hydrothermal pyrolysis. The CG-MS analysis of bio oil indicated hydrocarbon contents such as pentadecane, octadecane, hexadecane and benzene.

Okul Öncesi Eğitimde High Scope Modeli

OpenAIRE

Kotaman, Hüseyin

2009-01-01

Purpose of this study is to examine High Scope early childhood education system which was developed in USA. Accordingly historical reasons underlied the development of High Scope, systems’ educational theory, its’ curriculum and daily program routine, teachers’ characteristics and their responsibilities and High Scope’s evaluation system are defined. High Scope system base on Piaget’s constructivist theory. In this liberal educational system child learn through invent and const...

Scientific basis for nuclear waste management XX

International Nuclear Information System (INIS)

Gray, W.J.; Triay, I.R.

1997-01-01

The proceedings are divided into the following topical sections: Glass formulations and properties; Glass/water interactions; Cements in radioactive waste management; Ceramic and crystalline waste forms; Spent nuclear fuel; Waste processing and treatment; Radiation effects in ceramics, glasses, and nuclear waste materials; Waste package materials; Radionuclide solubility and speciation; Radionuclide sorption; Radionuclide transport; Repository backfill; Performance assessment; Natural analogues; Excess plutonium dispositioning; and Chernobyl-related waste disposal issues. Papers within scope have been processed separately for inclusion on the data base

Effect of aluminum and silicon reactants and process parameters on glass-ceramic waste form characteristics for immobilization of high-level fluorinel-sodium calcined waste

International Nuclear Information System (INIS)

Vinjamuri, K.

1993-06-01

In this report, the effects of aluminum and silicon reactants, process soak time and the initial calcine particle size on glass-ceramic waste form characteristics for immobilization of the high-level fluorinel-sodium calcined waste stored at the Idaho Chemical Processing Plant (ICPP) are investigated. The waste form characteristics include density, total and normalized elemental leach rates, and microstructure. Glass-ceramic waste forms were prepared by hot isostatically pressing (HIPing) a pre-compacted mixture of pilot plant fluorinel-sodium calcine, Al, and Si metal powders at 1050 degrees C, 20,000 psi for 4 hours. One of the formulations with 2 wt % Al was HIPed for 4, 8, 16 and 24 hours at the same temperature and pressure. The calcine particle size range include as calcined particle size smaller than 600 μm (finer than -30 mesh, or 215 μm Mass Median Diameter, MMD) and 180 μm (finer than 80 mesh, or 49 μm MMD)

Liquid abrasive grit blasting literature search and decontamination scoping tests report

International Nuclear Information System (INIS)

Ferguson, R.L.

1993-10-01

Past decontamination and solvent recovery activities at the Idaho Chemical Processing Plant (ICPP) have resulted in the accumulation of 1.5 million gallons of radioactively contaminated sodium-bearing liquid waste. Future decontamination activities at the ICPP could result in the production of 5 million gallons or more of sodium-bearing waste using the current decontamination techniques of chemical/water flushes and steam jet cleaning. With the curtailment of reprocessing at the ICPP, the focus of decontamination is shifting from maintenance for continued operation of the facilities to decommissioning. As decommissioning plans are developed, new decontamination methods must be used which result in higher decontamination factors and generate lower amounts of sodium-bearing secondary waste. The primary initiative of the WINCO Decontamination Development Program is the development of methods to eliminate/minimize the use of sodium-bearing decontamination chemicals. One method that was chosen for cold scoping studies during FY-93 was abrasive grit blasting. Abrasive grit blasting has been used in many industries and a vast amount of research and development has already been conducted. However, new grits, process improvements and ICPP applicability was investigated. This evaluation report is a summary of the research efforts and scoping tests using the liquid abrasive grit blasting decontamination technique. The purpose of these scoping tests was to determine the effectiveness of three different abrasive grits: plastic beads, glass beads and alumina oxide

Retrospection-Simulation-Revision: Approach to the Analysis of the Composition and Characteristics of Medical Waste at a Disaster Relief Site.

Science.gov (United States)

Zhang, Li; Wu, Lihua; Tian, Feng; Wang, Zheng

2016-01-01

A large amount of medical waste is produced during disaster relief, posing a potential hazard to the habitat and the environment. A comprehensive understanding of the composition and characteristics of medical waste that requires management is one of the most basic steps in the development of a plan for medical waste management. Unfortunately, limited reliable information is available in the open literature on the characteristics of the medical waste that is generated at disaster relief sites. This paper discusses the analysis of the composition and characteristics of medical waste at a disaster relief site using the retrospection-simulation-revision method. For this study, we obtained 35 medical relief records of the Wenchuan Earthquake, Sichuan, May 2008 from a field cabin hospital. We first present a retrospective analysis of the relief medical records, and then, we simulate the medical waste generated in the affected areas. We ultimately determine the composition and characteristics of medical waste in the affected areas using untreated medical waste to revise the composition of the simulated medical waste. The results from 35 cases showed that the medical waste generated from disaster relief consists of the following: plastic (43.2%), biomass (26.3%), synthetic fiber (15.3%), rubber (6.6%), liquid (6.6%), inorganic salts (0.3%) and metals (1.7%). The bulk density of medical relief waste is 249 kg/m3, and the moisture content is 44.75%. The data should be provided to assist the collection, segregation, storage, transportation, disposal and contamination control of medical waste in affected areas. In this paper, we wish to introduce this research method of restoring the medical waste generated in disaster relief to readers and researchers. In addition, we hope more disaster relief agencies will become aware of the significance of medical case recording and storing. This may be very important for the environmental evaluation of medical waste in disaster areas, as

The Sort on Radioactive Waste Type model: A method to sort single-shell tanks into characteristic groups

International Nuclear Information System (INIS)

Hill, J.G.; Simpson, B.C.

1994-04-01

The Sort on Radioactive Waste Type (SORWT) model presents a method to categorize Hanford Site single-shell tanks (SSTs) into groups of tank expected to exhibit similar chemical and physical characteristics based on their major waste types and processing histories. This model has identified 29 different waste-type groups encompassing 135 of the 149 SSTs and 93% of the total waste volume in SSTs. The remaining 14 SSTs and associated wastes could not be grouped according to the established criteria and were placed in an ungrouped category. This letter report will detail the assumptions and methodologies used to develop the SORWT model and present the grouping results. In the near future, the validity of the predicted groups will be statistically tested using analysis of variance of characterization data obtained from recent (post-1989) core sampling and analysis activities. In addition, the SORWT model will be used to project the nominal waste characteristics of entire waste type groups that have some recent characterization data available. These subsequent activities will be documented along with these initial results in a comprehensive, formal PNL report cleared for public release by September 1994

Incineration of radioactive waste

International Nuclear Information System (INIS)

Eid, C.

1985-01-01

The incineration process currently seems the most appropriate way to solve the problems encountered by the increasing quantities of low and medium active waste from nuclear power generation waste. Although a large number of incinerators operate in the industry, there is still scope for the improvement of safety, throughput capacity and reduction of secondary waste. This seminar intends to give opportunity to scientists working on the different aspects of incineration to present their most salient results and to discuss the possibilities of making headway in the management of LL/ML radioactive waste. These proceedings include 17 contributions ranging over the subjects: incineration of solid β-γ wastes; incineration of other radwastes; measurement and control of wastes; off-gas filtration and release. (orig./G.J.P.)

Scope and approach to management of mixed wastes: introduction to the session

International Nuclear Information System (INIS)

Ausmus, B.S.

1986-01-01

Mixed wastes are those that are termed both radioactive and chemically hazardous based on regulatory criteria in the United States. Historically, mixed wastes that could be classified as radioactive wastes were treated, stored, and disposed under statutes governing radioactive wastes. In recent years, it has become apparent that: (a) hazardous wastes are generated in nuclear facilities; (b) many wastes are both radioactive and chemically hazardous; and (c) the management of chemically hazardous wastes and mixed wastes requires reexamination of current waste treatment/disposal methods and development/implementation of modified methods. The purpose of this session is to discuss specific aspects of the mixed waste management problems and to provide a forum for discussion of the technical and institutional barriers to problem solutions. The paper addresses several mixed waste problems and current approaches to their solutions, including: (1) mixed waste management in fuel cycle facilities; (2) mixed waste management in a US Dept. of Energy production facility; and (3) mixed wastes impacts on 10CFR61 compliance. Technical and institutional approaches to mixed waste management are explored in three areas: (1) alternatives for treatment prior to shallow land disposal; (2) potential benefits of recovery of strategic/critical materials from mixed wastes; and (3) shallow land disposal system compatibilities/problems

Uncertainty analysis of the radiological characteristics of radioactive waste using a method based on log-normal distributions

International Nuclear Information System (INIS)

Gigase, Yves

2007-01-01

Available in abstract form only. Full text of publication follows: The uncertainty on characteristics of radioactive LILW waste packages is difficult to determine and often very large. This results from a lack of knowledge of the constitution of the waste package and of the composition of the radioactive sources inside. To calculate a quantitative estimate of the uncertainty on a characteristic of a waste package one has to combine these various uncertainties. This paper discusses an approach to this problem, based on the use of the log-normal distribution, which is both elegant and easy to use. It can provide as example quantitative estimates of uncertainty intervals that 'make sense'. The purpose is to develop a pragmatic approach that can be integrated into existing characterization methods. In this paper we show how our method can be applied to the scaling factor method. We also explain how it can be used when estimating other more complex characteristics such as the total uncertainty of a collection of waste packages. This method could have applications in radioactive waste management, more in particular in those decision processes where the uncertainty on the amount of activity is considered to be important such as in probability risk assessment or the definition of criteria for acceptance or categorization. (author)

Waste Feed Delivery Transfer System Analysis

Energy Technology Data Exchange (ETDEWEB)

JULYK, L.J.

2000-05-05

This document provides a documented basis for the required design pressure rating and pump pressure capacity of the Hanford Site waste-transfer system in support of the waste feed delivery to the privatization contractor for vitrification. The scope of the analysis includes the 200 East Area double-shell tank waste transfer pipeline system and the associated transfer system pumps for a11 Phase 1B and Phase 2 waste transfers from AN, AP, AW, AY, and A2 Tank Farms.

Waste Feed Delivery Transfer System Analysis

International Nuclear Information System (INIS)

JULYK, L.J.

2000-01-01

This document provides a documented basis for the required design pressure rating and pump pressure capacity of the Hanford Site waste-transfer system in support of the waste feed delivery to the privatization contractor for vitrification. The scope of the analysis includes the 200 East Area double-shell tank waste transfer pipeline system and the associated transfer system pumps for a11 Phase 1B and Phase 2 waste transfers from AN, AP, AW, AY, and A2 Tank Farms

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics

International Nuclear Information System (INIS)

Hulse, R.A.

1991-08-01

Planning for storage or disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of that waste to estimate volumes, radionuclide activities, and waste forms. Data from existing literature, disposal records, and original research were used to estimate the characteristics and project volumes and radionuclide activities to the year 2035. GTCC LLW is categorized as: nuclear utilities waste, sealed sources waste, DOE-held potential GTCC LLW; and, other generator waste. It has been determined that the largest volume of those wastes, approximately 57%, is generated by nuclear power plants. The Other Generator waste category contributes approximately 10% of the total GTCC LLW volume projected to the year 2035. Waste held by the Department of Energy, which is potential GTCC LLW, accounts for nearly 33% of all waste projected to the year 2035; however, no disposal determination has been made for that waste. Sealed sources are less than 0.2% of the total projected volume of GTCC LLW

The chemical/physical and microbiological characteristics of typical bath and laundry waste waters. [waste water reclamation during manned space flight

Science.gov (United States)

Hypes, W. D.; Batten, C. E.; Wilkins, J. R.

1974-01-01

Chemical/physical and microbiological characteristics are studied of typical bath and laundry waters collected during a 12 day test in which the untreated waste waters were reused for toilet flush. Most significant changes were found for ammonia, color, methylene blue active substances, phosphates, sodium, sulfates, total organic carbon, total solids, and turbidity in comparison with tap water baseline. The mean total number of microorganisms detected in the waste waters ranged from 1 million to 10 to the 7th power cells/m1 and the mean number of possible coliforms ranged from 10 to the 5th power to 1 million. An accumulation of particulates and an objectible odor were detected in the tankage used during the 12 day reuse of the untreated waste waters. The combined bath and laundry waste waters from a family of four provided 91 percent of the toilet flush water for the same family.

Mixed waste focus area alternative technologies workshop

International Nuclear Information System (INIS)

Borduin, L.C.; Palmer, B.A.; Pendergrass, J.A.

1995-01-01

This report documents the Mixed Waste Focus Area (MWFA)-sponsored Alternative Technology Workshop held in Salt Lake City, Utah, from January 24--27, 1995. The primary workshop goal was identifying potential applications for emerging technologies within the Options Analysis Team (OAT) ''wise'' configuration. Consistent with the scope of the OAT analysis, the review was limited to the Mixed Low-Level Waste (MLLW) fraction of DOE's mixed waste inventory. The Los Alamos team prepared workshop materials (databases and compilations) to be used as bases for participant review and recommendations. These materials derived from the Mixed Waste Inventory Report (MWIR) data base (May 1994), the Draft Site Treatment Plan (DSTP) data base, and the OAT treatment facility configuration of December 7, 1994. In reviewing workshop results, the reader should note several caveats regarding data limitations. Link-up of the MWIR and DSTP data bases, while representing the most comprehensive array of mixed waste information available at the time of the workshop, requires additional data to completely characterize all waste streams. A number of changes in waste identification (new and redefined streams) occurred during the interval from compilation of the data base to compilation of the DSTP data base with the end result that precise identification of radiological and contaminant characteristics was not possible for these streams. To a degree, these shortcomings compromise the workshop results; however, the preponderance of waste data was linked adequately, and therefore, these analyses should provide useful insight into potential applications of alternative technologies to DOE MLLW treatment facilities

CO2 pellet blasting literature search and decontamination scoping tests report

International Nuclear Information System (INIS)

Archibald, K.E.

1993-12-01

Past decontamination and solvent recovery activities at the Idaho Chemical Processing Plant (ICPP) have resulted in the accumulation of 1.5 million gallons of radioactively contaminated sodium-bearing liquid waste. Future decontamination activities at the ICPP could result in the production of 5 million gallons or more of sodium-bearing waste using current decontamination techniques. Chemical decontamination flushes have provided a satisfactory level of decontamination. However, this method generates large amounts of sodium-bearing secondary waste. Steam jet cleaning has also been used with a great deal of success but cannot be used on concrete or soft materials. With the curtailment of reprocessing at the ICPP, the focus of decontamination is shifting from maintenance for continued operation of the facilities to decommissioning. Treatment of sodium-bearing waste is a particularly difficult problem due to the high content of alkali metals in the sodium-bearing liquid waste. It requires a very large volume of cold chemical additive for calcination. In addition, the sodium content of the sodium-bearing waste exceeds the limit that can be incorporated into vitrified waste without the addition of glass-forming compounds (primarily silicon) to produce an acceptable immobilized waste form. The primary initiatives of the Decontamination Development Program is the development of methods to eliminate/minimize the use of sodium-bearing decontamination chemicals and to minimize all liquid decontamination wastes. One method chosen for cold scoping studies during FY-93 was CO 2 pellet blasting. CO 2 pellet blasting has been used extensively by commercial industries for general cleaning. However, using this method for decontamination of nuclear materials is a fairly new concept. The following report discusses the research and scoping tests completed on CO 2 pellet blasting

Waste segregation

International Nuclear Information System (INIS)

Clark, D.E.; Colombo, P.

1982-01-01

A scoping study has been undertaken to determine the state-of-the-art of waste segregation technology as applied to the management of low-level waste (LLW). Present-day waste segregation practices were surveyed through a review of the recent literature and by means of personal interviews with personnel at selected facilities. Among the nuclear establishments surveyed were Department of Energy (DOE) laboratories and plants, nuclear fuel cycle plants, public and private laboratories, institutions, industrial plants, and DOE and commercially operated shallow land burial sites. These survey data were used to analyze the relationship between waste segregation practices and waste treatment/disposal processes, to assess the developmental needs for improved segregation technology, and to evaluate the costs and benefits associated with the implementation of waste segregation controls. This task was planned for completion in FY 1981. It should be noted that LLW management practices are now undergoing rapid change such that the technology and requirements for waste segregation in the near future may differ significantly from those of the present day. 8 figures

Effect of incorporation of nutraceutical capsule waste of safflower oil in the mechanical characteristics of corn starch films

Directory of Open Access Journals (Sweden)

Camila de CAMPO

2016-01-01

Full Text Available Abstract Biodegradable films blends made of safflower oil nutraceutical capsules waste corn starch (20:4, 30:4, 40:4 and 50:4 were prepared. The objective of this study was to evaluate the influence of addition of different concentrations of safflower oil nutraceutical capsule waste in the mechanical properties (tensile strength, elongation at break, Young’s modulus and thickness of corn starch films. A decrease in tensile strength and Young’s modulus and an increase in elongation at break were observed with the increase in the content of the nutraceutical capsule waste. The results showed that the blends of safflower oil capsules waste-corn starch films demonstrated promising characteristics to form biodegradable films with different mechanical characteristics.

Laboratory test investigations on soil water characteristic curve and air permeability of municipal solid waste.

Science.gov (United States)

Shi, Jianyong; Wu, Xun; Ai, Yingbo; Zhang, Zhen

2018-05-01

The air permeability coefficient has a high correlation with the water content of municipal solid waste. In this study, continuous drying methodology using a tension meter was employed to construct the soil water characteristic curve of municipal solid waste (M-SWCC). The municipal solid waste air permeability test was conducted by a newly designed apparatus. The measured M-SWCC was well reproduced by the van Genuchten (V-G) model and was used to predict the parameters of typical points in M-SWCC, including saturated water content, field capacity, residual water content and water content at the inflection point. It was found that the M-SWCC was significantly influenced by void ratio. The final evaporation and test period of M-SWCC increase with the increase in void ratio of municipal solid waste. The evolution of air permeability coefficient with water content of municipal solid waste depicted three distinct characteristic stages. It was observed that the water contents that corresponded to the two cut-off points of the three stages were residual water content and water content at the inflection point, respectively. The air permeability coefficient of municipal solid waste decreased with the increase of the water content from zero to the residual water content. The air permeability coefficient was almost invariable when the water content increased from residual water content to the water content at the inflection point. When the water content of municipal solid waste exceeded the water content at the inflection point, the air permeability coefficient sharply decreased with the increase of water content.

Scoping corrosion tests on candidate waste package basket materials for the Yucca Mountain project

International Nuclear Information System (INIS)

Konynenburg, R.A. van; Curtis, P.G.; Summers, T.S.E.

1998-03-01

A scoping corrosion test was performed on candidate waste package basket materials. The corrosion medium was a pH-buffered solution of chemical species expected to be produced by radiolysis. The test was conducted at 90 C for 96 hours. Samples included aluminum-, copper-, stainless steel- and zirconium-based metallic materials and several ceramics, incorporating neutron-absorbing elements. Sample weight losses and solution chemical changes were measured. Both corrosion of the host materials and dissolution of the neutron-absorbing elements were studied. The ceramics and the zirconium-based materials underwent only minor corrosion. The stainless steel-based materials performed well except for a welded sample. The aluminum- and copper-based materials exhibited the highest corrosion rates. Boron dissolution depends on its chemical form. Boron oxide and many metal borides dissolve readily in acidic solutions while high-chromium borides and boron carbide, though thermodynamically unstable, exhibit little dissolution in short times. The results of solution chemical analyses were consistent with this. Gadolinium did not dissolve significantly from monazite, and hafnium showed little dissolution from a variety of host materials, in keeping with its low solubility

Formulation and Characterization of Waste Glasses with Varying Processing Temperature

Energy Technology Data Exchange (ETDEWEB)

Kim, Dong-Sang; Schweiger, M. J.; Rodriguez, Carmen P.; Lepry, William C.; Lang, Jesse B.; Crum, Jarrod V.; Vienna, John D.; Johnson, Fabienne; Marra, James C.; Peeler, David K.

2011-10-17

This report documents the preliminary results of glass formulation and characterization accomplished within the finished scope of the EM-31 technology development tasks for WP-4 and WP-5, including WP-4.1.2: Glass Formulation for Next Generation Melter, WP-5.1.2.3: Systematic Glass Studies, and WP-5.1.2.4: Glass Formulation for Specific Wastes. This report also presents the suggested studies for eventual restart of these tasks. The initial glass formulation efforts for the cold crucible induction melter (CCIM), operating at {approx}1200 C, with selected HLW (AZ-101) and LAW (AN-105) successfully developed glasses with significant increase of waste loading compared to that is likely to be achieved based on expected reference WTP formulations. Three glasses formulated for AZ-101HLW and one glass for AN-105 LAW were selected for the initial CCIM demonstration melter tests. Melter tests were not performed within the finished scope of the WP-4.1.2 task. Glass formulations for CCIM were expanded to cover additional HLWs that have high potential to successfully demonstrate the unique advantages of the CCIM technologies based on projected composition of Hanford wastes. However, only the preliminary scoping tests were completed with selected wastes within the finished scope. Advanced glass formulations for the reference WTP melter, operating at {approx}1200 C, were initiated with selected specific wastes to determine the estimated maximum waste loading. The incomplete results from these initial formulation efforts are summarized. For systematic glass studies, a test matrix of 32 high-aluminum glasses was completed based on a new method developed in this study.

Formulation and Characterization of Waste Glasses with Varying Processing Temperature

International Nuclear Information System (INIS)

Kim, Dong-Sang; Schweiger, M.J.; Rodriguez, Carmen P.; Lepry, William C.; Lang, Jesse B.; Crum, Jarrod V.; Vienna, John D.; Johnson, Fabienne; Marra, James C.; Peeler, David K.

2011-01-01

This report documents the preliminary results of glass formulation and characterization accomplished within the finished scope of the EM-31 technology development tasks for WP-4 and WP-5, including WP-4.1.2: Glass Formulation for Next Generation Melter, WP-5.1.2.3: Systematic Glass Studies, and WP-5.1.2.4: Glass Formulation for Specific Wastes. This report also presents the suggested studies for eventual restart of these tasks. The initial glass formulation efforts for the cold crucible induction melter (CCIM), operating at ∼1200 C, with selected HLW (AZ-101) and LAW (AN-105) successfully developed glasses with significant increase of waste loading compared to that is likely to be achieved based on expected reference WTP formulations. Three glasses formulated for AZ-101HLW and one glass for AN-105 LAW were selected for the initial CCIM demonstration melter tests. Melter tests were not performed within the finished scope of the WP-4.1.2 task. Glass formulations for CCIM were expanded to cover additional HLWs that have high potential to successfully demonstrate the unique advantages of the CCIM technologies based on projected composition of Hanford wastes. However, only the preliminary scoping tests were completed with selected wastes within the finished scope. Advanced glass formulations for the reference WTP melter, operating at ∼1200 C, were initiated with selected specific wastes to determine the estimated maximum waste loading. The incomplete results from these initial formulation efforts are summarized. For systematic glass studies, a test matrix of 32 high-aluminum glasses was completed based on a new method developed in this study.

Assessment of radiological properties of wastes from urban decontamination procedures

International Nuclear Information System (INIS)

Da Silva, D.N.G.; Guimarães, J.R.D.; Rochedo, E.R.R.; Rochedo, P.R.R.; De Luca, C.

2015-01-01

One important activity associated to urban areas contaminated from accidental releases to the atmosphere of nuclear power plants is the management of radioactive wastes generated from decontamination procedures. This include the collection, conditioning, packing, transport and temporary/final disposition. The final destination is defined usually through a political decision. Thus, transport of packed radioactive wastes shall depend on decisions not just under the scope of radiological protection issues. However, the simulations performed to assess doses for the public and decontamination workers allows the estimate of radiological aspects related to the waste generated and these characteristics may be included in a multi-criteria decision tool aiming to support, under the radiological protection point of view, the decision-making process on post-emergency procedures. Important information to decision makers are the type, amount and activity concentration of wastes. This work describes the procedures to be included in the urban area model to account for the assessment of qualitative and quantitative description of wastes. The results will allow the classification of different procedures according to predefined criteria that shall then feed the multi-criteria assessment tool, currently under development, considering basic radiological protection aspects of wastes generated by the different available cleanup procedures on typical tropical urban environments. (authors)

Shallow land burial of low-level radioactive waste

International Nuclear Information System (INIS)

Cannon, J.B.; Jacobs, D.G.; Lee, D.W.

1986-02-01

The performance objectives included in regulations for disposal of low-level radioactive waste (10 CFR 61 for commercial waste and DOE Order 5820.2 for defense waste) are generic principles that generate technical requirements which must be factored into each phase of the development and operation of a shallow land burial facility. These phases include a determination of the quantity and characteristics of the waste, selection of a site and appropriate facility design, use of sound operating practices, and closure of the facility. The collective experience concerning shallow land burial operations has shown that achievement of the performance objectives (specifically, waste isolation and radionuclide containment) requires a systems approach, factoring into consideration the interrelationships of the phases of facility development and operation and their overall impact on performance. This report presents the technical requirements and procedures for the development and operation of a shallow land burial facility for low-level radioactive waste. The systems approach is embodied in the presentation. The report is not intended to be an instruction manual; rather, emphasis is placed on understanding the technical requirements and knowing what information and analysis are needed for making informed choices to meet them. A framework is developed for using the desired site characteristics to locate potentially suitable sites. The scope of efforts necessary for characterizing a site is then described and the range of techniques available for site characterization is identified. Given the natural features of a site, design options for achieving the performance objectives are discussed, as are the operating practices, which must be compatible with the design. Site closure is presented as functioning to preserve the containment and isolation provided at earlier stages of the development and operation of the facility

Integrated data base for 1993: US spent fuel and radioactive waste inventories, projections, and characteristics. Revision 9

Energy Technology Data Exchange (ETDEWEB)

Klein, J.A.; Storch, S.N.; Ashline, R.C. [and others

1994-03-01

The Integrated Data Base (IDB) Program has compiled historic data on inventories and characteristics of both commercial and DOE spent fuel; also, commercial and U.S. government-owned radioactive wastes through December 31, 1992. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest U.S. Department of Energy/Energy Information Administration (DOE/EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste (HLW), transuranic (TRU), waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) LLW. For most of these categories, current and projected inventories are given through the calendar-year (CY) 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal.

RETRIEVING SUSPECT TRANSURANIC WASTE FROM THE HANFORD BURIAL GROUNDS PROGRESS PLANS AND CHALLENGES

International Nuclear Information System (INIS)

FRENCH, M.S.

2006-01-01

This paper describes the scope and status of the program for retrieval of suspect transuranic (TRU) waste stored in the Hanford Site low-level burial grounds. Beginning in 1970 and continuing until the late 1980's, waste suspected of containing significant quantities of transuranic isotopes was placed in ''retrievable'' storage in designated modules in the Hanford burial grounds, with the intent that the waste would be retrieved when a national repository for disposal of such waste became operational. Approximately 15,000 cubic meters of waste, suspected of being TRU, was placed in storage modules in four burial grounds. With the availability of the national repository (the Waste Isolation Pilot Plant), retrieval of the suspect TRU waste is now underway. Retrieval efforts, to date, have been conducted in storage modules that contain waste, which is in general, contact-handled, relatively new (1980's and later), is stacked in neat, engineered configurations, and has a relatively good record of waste characteristics. Even with these optimum conditions, retrieval personnel have had to deal with a large number of structurally degraded containers, radioactive contamination issues, and industrial hazards (including organic vapors). Future retrieval efforts in older, less engineered modules are expected to present additional hazards and difficult challenges

Nuclear waste incineration technology status

International Nuclear Information System (INIS)

Ziegler, D.L.; Lehmkuhl, G.D.; Meile, L.J.

1981-01-01

The incinerators developed and/or used for radioactive waste combustion are discussed and suggestions are made for uses of incineration in radioactive waste management programs and for incinerators best suited for specific applications. Information on the amounts and types of radioactive wastes are included to indicate the scope of combustible wastes being generated and in existence. An analysis of recently developed radwaste incinerators is given to help those interested in choosing incinerators for specific applications. Operating information on US and foreign incinerators is also included to provide additional background information. Development needs are identified for extending incinerator applications and for establishing commercial acceptance

Nuclear waste incineration technology status

Energy Technology Data Exchange (ETDEWEB)

Ziegler, D.L.; Lehmkuhl, G.D.; Meile, L.J.

1981-07-15

The incinerators developed and/or used for radioactive waste combustion are discussed and suggestions are made for uses of incineration in radioactive waste management programs and for incinerators best suited for specific applications. Information on the amounts and types of radioactive wastes are included to indicate the scope of combustible wastes being generated and in existence. An analysis of recently developed radwaste incinerators is given to help those interested in choosing incinerators for specific applications. Operating information on US and foreign incinerators is also included to provide additional background information. Development needs are identified for extending incinerator applications and for establishing commercial acceptance.

Solid low-level waste certification strategy

International Nuclear Information System (INIS)

Smith, M.A.

1991-08-01

The purpose of the Solid Low-Level Waste (SLLW) Certification Program is to provide assurance that SLLW generated at the ORNL meets the applicable waste acceptance criteria for those facilities to which the waste is sent for treatment, handling, storage, or disposal. This document describes the strategy to be used for certification of SLLW or ORNL. The SLLW Certification Program applies to all ORNL operations involving the generation, shipment, handling, treatment, storage and disposal of SLLW. Mixed wastes, containing both hazardous and radioactive constituents, and transuranic wastes are not included in the scope of this document. 13 refs., 3 figs

Identification of potential transuranic waste tanks at the Hanford Site

Energy Technology Data Exchange (ETDEWEB)

Colburn, R.P.

1995-05-05

The purpose of this document is to identify potential transuranic (TRU) material among the Hanford Site tank wastes for possible disposal at the Waste Isolation Pilot Plant (WIPP) as an alternative to disposal in the high-level waste (HLW) repository. Identification of such material is the initial task in a trade study suggested in WHC-EP-0786, Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The scope of this document is limited to the identification of those tanks that might be segregated from the HLW for disposal as TRU, and the bases for that selection. It is assumed that the tank waste will be washed to remove soluble inert material for disposal as low-level waste (LLW), and the washed residual solids will be vitrified for disposal. The actual recommendation of a disposal strategy for these materials will require a detailed cost/benefit analysis and is beyond the scope of this document.

Identification of potential transuranic waste tanks at the Hanford Site

International Nuclear Information System (INIS)

Colburn, R.P.

1995-01-01

The purpose of this document is to identify potential transuranic (TRU) material among the Hanford Site tank wastes for possible disposal at the Waste Isolation Pilot Plant (WIPP) as an alternative to disposal in the high-level waste (HLW) repository. Identification of such material is the initial task in a trade study suggested in WHC-EP-0786, Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The scope of this document is limited to the identification of those tanks that might be segregated from the HLW for disposal as TRU, and the bases for that selection. It is assumed that the tank waste will be washed to remove soluble inert material for disposal as low-level waste (LLW), and the washed residual solids will be vitrified for disposal. The actual recommendation of a disposal strategy for these materials will require a detailed cost/benefit analysis and is beyond the scope of this document

Inventory and characteristics of current and projected low-level radioactive materials and waste in the United States

International Nuclear Information System (INIS)

Bisaria, A.; Bugos, R.G.; Pope, R.B.; Salmon, R.; Storch, S.N.; Lester, P.B.

1994-01-01

The Integrated Data Base (IDB), under US Department of Energy (DOE) funding and guidance, provides an annual update of compiled data on current and projected inventories and characteristics of DOE and commercially owned radioactive wastes. The data base addresses also the inventories of DOE and commercial spent fuel. These data are derived from reliable information from government sources, open literature, technical reports, and direct contacts. The radioactive materials considered are spent nuclear fuel, high-level waste (HLW), transuranic (TRU) waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, and mixed-LLW. This paper primarily focuses on LLW inventory and characterization

Boundary spanning by nurse managers: effects of managers' characteristics and scope of responsibility on teamwork.

Science.gov (United States)

Meyer, Raquel M; O'Brien-Pallas, Linda; Doran, Diane; Streiner, David; Ferguson-Paré, Mary; Duffield, Christine

2014-06-01

Increasing role complexity has intensified the work of managers in supporting healthcare teams. This study examined the influence of front-line managers' characteristics and scope of responsibility on teamwork. Scope of responsibility considers the breadth of the manager's role. A descriptive, correlational design was used to collect cross-sectional survey and administrative data in four acute care hospitals. A convenience sample of 754 staff completed the Relational Coordination Scale as a measure of teamwork that focuses on the quality of communication and relationships. Nurses (73.9%), allied health professionals (14.7%) and unregulated staff (11.7%) worked in 54 clinical areas, clustered under 30 front-line managers. Data were analyzed using hierarchical linear modelling. Leadership practices, clinical support roles and compressed operational hours had positive effects on teamwork. Numbers of non-direct report staff and areas assigned had negative effects on teamwork. Teamwork did not vary by span, managerial experience, worked hours, occupational diversity or proportion of full-time employees. Large, acute care teaching hospitals can enable managers to foster teamwork by enhancing managers' leadership practices, redesigning the flow or reporting structure for non-direct reports, optimizing managerial hours relative to operational hours, allocating clinical support roles, reducing number of areas assigned and, potentially, introducing co-manager models. Copyright © 2014 Longwoods Publishing.

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

Thermal characteristics of rocks for high-level waste repository

International Nuclear Information System (INIS)

Shimooka, Kenji; Ishizaki, Kanjiro; Okamoto, Masamichi; Kumata, Masahiro; Araki, Kunio; Amano, Hiroshi

1980-12-01

Heat released by the radioactive decay of high-level waste in an underground repository causes a long term thermal disturbance in the surrounding rock mass. Several rocks constituting geological formations in Japan were gathered and specific heat, thermal conductivity, thermal expansion coefficient and compressive strength were measured. Thermal analysis and chemical analysis were also carried out. It was found that volcanic rocks, i.e. Andesite and Basalt had the most favorable thermal characteristics up to around 1000 0 C and plutonic rock, i.e. Granite had also favorable characteristics under 573 0 C, transition temperature of quartz. Other igneous rocks, i.e. Rhyolite and Propylite had a problem of decomposition at around 500 0 C. Sedimentary rocks, i.e. Zeolite, Tuff, Sandstone and Diatomite were less favorable because of their decomposition, low thermal conductivity and large thermal expansion coefficient. (author)

Legal assistance on the application of public procurement rules in the waste sector

DEFF Research Database (Denmark)

Andrecka, Marta

2016-01-01

The report presents the results of a study investigating the application of public procurement rules in the municipal waste sector across the European Union conducted by Ramboll Management Consulting for the European Commission (DG GROW). The study is part of a process launched by the European...... Commission to analyse the application of public procurement rules in different market sectors. The scope of the study was set by the definition of municipal [solid] waste as presented in the Waste Framework Directive.1 The geographical scope of data collection was focused on seven Member States: Germany...

Emissions Characteristics of Small Diesel Engine Fuelled by Waste Cooking Oil

Directory of Open Access Journals (Sweden)

Khalid Amir

2014-07-01

Full Text Available Biodiesel is an alternative, decomposable and biological-processed fuel that has similar characteristics with mineral diesel which can be used directly into diesel engines. However, biodiesel has oxygenated, more density and viscosity compared to mineral diesel. Despite years of improvement attempts, the key issue in using waste cooking oil-based fuels is oxidation stability, stoichiometric point, bio-fuel composition, antioxidants on the degradation and much oxygen with comparing to diesel gas oil. Thus, the improvement of emission exhausted from diesel engines fueled by biodiesel derived from waste cooking oil (WCO is urgently required to meet the future stringent emission regulations. The purpose of this research is to investigate the influences of WCO blended fuel and combustion reliability in small engine on the combustion characteristics and exhaust emissions. The engine speed was varied from 1500-2500 rpm and WCO blending ratio from 5-15 vol% (W5-W15. Increased blends of WCO ratio is found to influences to the combustion process, resulting in decreased the HC emissions and also other exhaust emission element. The improvement of combustion process is expected to be strongly influenced by oxygenated fuel in biodiesel content.

Hydrogen venting characteristics of commercial carbon-composite filters and applications to TRU waste

International Nuclear Information System (INIS)

Callis, E.L.; Marshall, R.S.; Cappis, J.H.

1997-04-01

The generation of hydrogen (by radiolysis) and of other potentially flammable gases in radioactive wastes which are in contact with hydrogenous materials is a source of concern, both from transportation and on-site storage considerations. Because very little experimental data on the generation and accumulation of hydrogen was available in actual waste materials, work was initiated to experimentally determine factors affecting the concentration of hydrogen in the waste containers, such as the hydrogen generation rate, (G-values) and the rate of loss of hydrogen through packaging and commercial filter-vents, including a new design suitable for plastic bags. This report deals only with the venting aspect of the problem. Hydrogen venting characteristics of two types of commercial carbon-composite filter-vents, and two types of PVC bag closures (heat-sealed and twist-and-tape) were measured. Techniques and equipment were developed to permit measurement of the hydrogen concentration in various layers of actual transuranic (TRU) waste packages, both with and without filter-vents. A test barrel was assembled containing known configuration and amounts of TRU wastes. Measurements of the hydrogen in the headspace verified a hydrogen release model developed by Benchmark Environmental Corporation. These data were used to calculate revised wattage Emits for TRU waste packages incorporating the new bag filter-vent

Comparative analysis of risk characteristics of nuclear waste repositories and other disposal facilities

International Nuclear Information System (INIS)

Lindell, M.K.; Earle, T.C.; Nealey, S.M.

1981-06-01

Three fundamental questions concerning public perception of the measurement of radioactive wastes were addressed in this report. The first question centered on the perceived importance of nuclear waste management as a public issue: how important is nuclear waste management relative to other technological and scientific issues; do different segments of the public disagree on its importance; the second question concerned public attitudes toward a nuclear waste disposal facility: how great a risk to health and safety is a nuclear waste disposal facility relative to other industrial facilities; is there disagreement on its riskiness among various public groups; the third question pertained to the aspects of risks that affect overall risk perception: what are the qualitative aspects of a nuclear waste disposal facility that contribute to overall perceptions of risk; do different segments of the population associate different risk characteristics with hazardous facilities. The questions follow from one another: is the issue important; given the importance of the issue, is the facility designed to deal with it considered risky; given the riskiness of the facility, why is it considered risky. Also addressed in this report, and a main focus of its findings, were the patterns of differences among respondent groups on each of these questions

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

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

Identification of influencing municipal characteristics regarding household waste generation and their forecasting ability in Biscay.

Science.gov (United States)

Oribe-Garcia, Iraia; Kamara-Esteban, Oihane; Martin, Cristina; Macarulla-Arenaza, Ana M; Alonso-Vicario, Ainhoa

2015-05-01

The planning of waste management strategies needs tools to support decisions at all stages of the process. Accurate quantification of the waste to be generated is essential for both the daily management (short-term) and proper design of facilities (long-term). Designing without rigorous knowledge may have serious economic and environmental consequences. The present works aims at identifying relevant socio-economic features of municipalities regarding Household Waste (HW) generation by means of factor models. Factor models face two main drawbacks, data collection and identifying relevant explanatory variables within a heterogeneous group. Grouping similar characteristics observations within a group may favour the deduction of more robust models. The methodology followed has been tested with Biscay Province because it stands out for having very different municipalities ranging from very rural to urban ones. Two main models are developed, one for the overall province and a second one after clustering the municipalities. The results prove that relating municipalities with specific characteristics, improves the results in a very heterogeneous situation. The methodology has identified urban morphology, tourism activity, level of education and economic situation as the most influencing characteristics in HW generation. Copyright © 2015 The Authors. Published by Elsevier Ltd.. All rights reserved.

Chemistry and technology of radioactive waste management - the IAEA perspective

International Nuclear Information System (INIS)

Efremenkov, V.M.; )

2003-01-01

The paper refers the consideration of chemical composition of radioactive waste in selection of particular method and technology for waste treatment and conditioning, importance of physico-chemical parameters of waste processing techniques for optimisation of waste processing to produce waste form of appropriate quality. Consideration of waste chemistry is illustrated by several IAEA activities on radioactive waste management and by outlining the scope of some selected technical reports on different waste management subjects. Different components of the IAEA activities on radioactive waste management and on technology transfer are presented and discussed. (author)

Characteristics of Waste Plastics Pyrolytic Oil and Its Applications as Alternative Fuel on Four Cylinder Diesel Engines

Directory of Open Access Journals (Sweden)

Nosal Nugroho Pratama

2014-02-01

Full Text Available Waste plastics recycling using pyrolysis method is not only able to decrease a number of environment pollutant but also able to produce economical and high quality hydrocarbon products. Two experiments were conducted to completely study Waste Plastic Pyrolytic Oil (WPPO characteristics and its applications.  First experiment investigated oil characteristics derived from pyrolysis process in two stages batch reactors: pyrolysis and catalytic reforming reactor, at maximum temperature 500oC and 450oC respectively. Waste Polyethylene (PE, Polypropylene (PP, Polystyrene (PS, Polyethylene Terepthalate (PET and others were used as raw material. Nitrogen flow rate at 0.8 l/minutes was used to increase oil weight percentage. Indonesian natural zeolite was used as catalyst. Then, second experiment was carried out on Diesel Engine Test Bed (DETB used blending of WPPO and Biodiesel fuel with a volume ratio of 1:9. This experiment was specifically conducted to study how much potency of blending of WPPO and biodiesel in diesel engine. The result of first experiment showed that the highest weight percentage of WPPO derived from mixture of PE waste (50%wt, PP waste (40%wt and PS waste (10%wt is 45.13%wt. The more weight percentage of PE in feedstock effected on the less weight percentage of WPPO, the more percentage of C12-C20 content in WPPO and the higher calorific value of WPPO. Characteristics of WPPO such as, Specific Gravity, Flash point, Pour Point, Kinematic Viscosity, Calorific value and percentage of C12-C20 showed interesting result that WPPO could be developed as alternative fuel on diesel fuel blending due to the proximity of their characteristics. Performance of diesel engine using blending of WPPO and biodiesel on second experiment gave good result so the WPPO will have great potency to be valuable alternative liquid fuel in future, especially on stationary diesel engine and transportation engine application.

Measuring safety culture in Dutch primary care: psychometric characteristics of the SCOPE-PC questionnaire.

Science.gov (United States)

Verbakel, Natasha J; Zwart, Dorien L M; Langelaan, Maaike; Verheij, Theo J M; Wagner, Cordula

2013-09-17

Patient safety has been a priority in primary healthcare in the last years. The prevailing culture is seen as an important condition for patient safety in practice and several tools to measure patient safety culture have therefore been developed. Although Dutch primary care consists of different professions, such as general practice, dental care, dietetics, physiotherapy and midwifery, a safety culture questionnaire was only available for general practices. The purpose of this study was to modify and validate this existing questionnaire to a generic questionnaire for all professions in Dutch primary care. A validated Dutch questionnaire for general practices was modified to make it usable for all Dutch primary care professions. Subsequently, this questionnaire was administered to a random sample of 2400 practices from eleven primary care professions. The instrument's factor structure, reliability and validity were examined using confirmatory and explorative factor analyses. 921 questionnaires were returned. Of these, 615 were eligible for factor analysis. The resulting SCOPE-PC questionnaire consisted of seven dimensions: 'open communication and learning from errors', 'handover and teamwork', 'adequate procedures and working conditions', 'patient safety management', 'support and fellowship', 'intention to report events' and 'organisational learning' with a total of 41 items. All dimensions had good reliability with Cronbach's alphas ranging from 0.70-0.90, and the questionnaire had a good construct validity. The SCOPE-PC questionnaire has sound psychometric characteristics for use by the different professions in Dutch primary care to gain insight in their safety culture.

Research on base rock mechanic characteristics of caverns for radioactive waste disposal

International Nuclear Information System (INIS)

Isei, Takehiro; Katsuyama, Kunihisa; Seto, Masahiro; Ogata, Yuji; Utagawa, Manabu

1997-01-01

It has been considered that underground space is mechanically stable as compared with on the ground, and superior for storing radioactive waste for long period. However, in order to utilize underground space for the place of radioactive waste disposal, its long term stability such as the aseismatic ability of base rocks must be ensured, and for this purpose, it is necessary to grasp the mechanical characteristics of the base rocks around caverns, and to advance the technology for measuring and evaluating minute deformation and earth pressure change. In this research, the study on the fracture mechanics characteristics of base rocks and the development of the technology for measuring long terms stress change of base rocks were carried out. In this research, what degree the memory of past stress is maintained by rocks was presumed by measuring AE and strain when stress was applied to rock test pieces. The rocks tested were tuff, sandstone and granite. The experimental method and the experimental results of the prestress by AE method and DRA are reported. (K.I.)

Analysis on Physical Characteristics of Rural Solid Waste in Dongjiang River Source Area, China

Directory of Open Access Journals (Sweden)

WANG Tao

2014-06-01

Full Text Available Dongjiang river is the source of drinking water of Guangdong Province and Hongkong, and the source area includes three counties in Ganzhou city of Jiangxi Province: Xunwu, Anyuan and Dingnan. Three typical villages were chosen in Dongjiang river source area to investigate the producing quantity and physical characteristics of rural solid waste. Results of investigation showed that the dominant ingredient in rural solid waste in Dongjiang river source area was kitchen waste, taking over 60%, followed by dust, reaching 12%, while other components took less than 10%. The per-capita producing quantity of solid waste of county-level village was 0.2~0.47 kg·d -1 and averaged by 0.36 kg·d -1, while that of town-level village was 0.18~0.35 kg· d -1, averaged by 0.29 kg· d -1 and that of hamlet was 0.07~0.33 kg· d -1, averaged by 0.17 kg· d -1. Water content in rural mixed solid waste of investigated area was significantly linear with percentage of kitchen waste in the mixed waste(R 2 =0.626, P=0.019. The average calorie wasaround 2 329 kJ·kg -1, which indicated that the rural solid waste in Dongjiang river source area was not suitable for incineration disposal directly.

Hanford Site annual waste reduction report

International Nuclear Information System (INIS)

Nichols, D.H.

1992-03-01

The US Department of Energy (DOE), Richland Field Office (RL) has developed and implemented a Hanford Site Waste Minimization and Pollution Prevention Awareness Plan that provides overall guidance and direction on waste minimization and pollution prevention awareness to the four contractors who manage and operate the Hanford Site for the RL. Waste reduction at the RL will be accomplished by following a hierarchy of environmental protection practices. First, waste generation will be eliminated or minimized through source reduction. Second, potential waste materials that cannot be eliminated or minimized will be recycled (i.e., used, reused, or reclaimed). Third, all waste that is nevertheless generated will be treated to reduce volume, toxicity, or mobility before storage or disposal. The scope of this waste reduction program will include nonhazardous, hazardous, radioactive mixed, and radioactive wastes

Description of the Northwest hazardous waste site data base and preliminary analysis of site characteristics

International Nuclear Information System (INIS)

Woodruff, D.L.; Hartz, K.E.; Triplett, M.B.

1988-08-01

The Northwest Hazardous Waste RD and D Center (the Center) conducts research, development, and demonstration (RD and D) activities for hazardous and radioactive mixed-waste technologies applicable to remediating sites in the states of Idaho, Montana, Oregon, and Washington. To properly set priorities for these RD and D activities and to target development efforts it is necessary to understand the nature of the sites requiring remediation. A data base of hazardous waste site characteristics has been constructed to facilitate this analysis. The data base used data from EPA's Region X Comprehensive Environmental Response, Compensation, and Liability Information System (CERCLIS) and from Preliminary Assessment/Site Investigation (PA/SI) forms for sites in Montana. The Center's data base focuses on two sets of sites--those on the National Priorities List (NPL) and other sites that are denoted as ''active'' CERCLIS sites. Active CERCLIS sites are those sites that are undergoing active investigation and analysis. The data base contains information for each site covering site identification and location, type of industry associated with the site, waste categories present (e.g., heavy metals, pesticides, etc.), methods of disposal (e.g., tanks, drums, land, etc.), waste forms (e.g., liquid, solid, etc.), and hazard targets (e.g., surface water, groundwater, etc.). As part of this analysis, the Northwest region was divided into three geographic subregions to identify differences in disposal site characteristics within the Northwest. 2 refs., 18 figs., 5 tabs

Integrated Data Base report--1993: U.S. spent nuclear fuel and radioactive waste inventories, projections, and characteristics. Revision 10

Energy Technology Data Exchange (ETDEWEB)

1994-12-01

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and DOE spent nuclear fuel; also, commercial and US government-owned radioactive wastes through December 31, 1993. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 256 refs., 38 figs., 141 tabs.

Integrated Data Base report--1993: U.S. spent nuclear fuel and radioactive waste inventories, projections, and characteristics. Revision 10

International Nuclear Information System (INIS)

1994-12-01

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and DOE spent nuclear fuel; also, commercial and US government-owned radioactive wastes through December 31, 1993. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 256 refs., 38 figs., 141 tabs

The Sort on Radioactive Waste Type model: A method to sort single-shell tanks into characteristic groups. Revision 1

International Nuclear Information System (INIS)

Hill, J.G.; Simpson, B.C.

1994-08-01

The Sort on Radioactive Waste Type (SORWT) model presents a method to categorize Hanford Site single-shell tanks (SSTs) into groups of tanks expected to exhibit similar chemical and physical characteristics based on their major waste types and processing histories. This model has identified 29 different waste-type groups encompassing 135 of the 149 SSTs and 93% of the total waste volume in SSTs. The remaining 14 SSTs and associated wastes could not be grouped according to the established criteria and were placed in an ungrouped category. This letter report will detail the assumptions and methodologies used to develop the SORWT model and present the grouping results. Included with this report is a brief description and approximate compositions of the single-shell tank waste types. In the near future, the validity of the predicted groups will be statistically tested using analysis of variance of characterization data obtained from recent (post-1989) core sampling and analysis activities. In addition, the SORWT model will be used to project the nominal waste characteristics of entire waste type groups that have some recent characterization data available. These subsequent activities will be documented along with these initial results in a comprehensive, formal PNL report cleared for public release by September 1994

Compost feedstock characteristics and ratio modelling for organic waste materials co-composting in Malaysia.

Science.gov (United States)

Chai, E W; H'ng, P S; Peng, S H; Wan-Azha, W M; Chin, K L; Chow, M J; Wong, W Z

2013-01-01

In Malaysia, large amounts of organic materials, which lead to disposal problems, are generated from agricultural residues especially from palm oil industries. Increasing landfill costs and regulations, which limit many types of waste accepted at landfills, have increased the interest in composting as a component of waste management. The objectives of this study were to characterize compost feedstock properties of common organic waste materials available in Malaysia. Thus, a ratio modelling of matching ingredients for empty fruit bunches (EFBs) co-composting using different organic materials in Malaysia was done. Organic waste materials with a C/N ratio of composting. The outcome of this study suggested that the percentage of EFB ranged between 50% and 60%, which is considered as the ideal mixing ratio in EFB co-composting. Conclusively, EFB can be utilized in composting if appropriate feedstock in term of physical and chemical characteristics is coordinated in the co-composting process.

Predicting the calorific value of refuse derived fuel from the characteristics of municipal solid waste

International Nuclear Information System (INIS)

Sivapalan Kathiravale; Muhd Noor Muhd Yunus; Mohamad Puad Abu; Mohamad Azman Che Mat Isa; Mohd Fairus Abdul Farid; Norasalwa Zakaria; Khaironie Mohd Takip; Rohyiza Ba'an

2006-01-01

The Imposing need to manage the municipal solid waste generated by society in a proper manner has urged municipalities to look into new management methods, which are not only environmentally friendly but also economically profitable. One such way is by converting this waste material into fuel. Currently, Kajang in the State of Selangor, Malaysia, generates about 700 tons of Municipal Solid Waste (MSW) a day. Due to rapid development, lack of land area for new landfill and the environmental impact of raw landfills, the local municipal council has collaborated with a local company in the management of this waste. The company has proposed to convert the MSW to Refuse Derived Fuel (RDF). In view of this, a pilot plant to convert MSW to RDF was erected by the company and begun operation in January 2002. This pilot plant has the capability of converting 15 tons of MSW to 5 tons of RDF. At the same time studies, have been carried out to assess the plant performance, the flue gas analysis, and also the MSW and RDF characteristic. This paper will highlight the findings of the MSW and RDF characterization work carried out over the past year. Sampling and analysis was carried in accordance with ASTM standards. Results of the waste analysis showed that the calorific value of the resulting RDF could be predicted from the physical characteristics as well as the moisture content. Regression analysis on the available data has been used to create equations relating the proximate composition and moisture content of the incoming municipal solid waste to the calorific value of the RDF

Managing nuclear wastes: an overview of the issues

International Nuclear Information System (INIS)

Cummings, R.G.; Utton, A.E.

1981-01-01

The issues involving nuclear waste management are reviewed. The author points out the need for a critical overview of research priorities concerning nuclear waste management (NWM), and he discusses the uncertainties surrounding the scope of the problem (i.e., the controversy concerning the extent of dangers to public health and safety associated with the transport and storage of nuclear wastes). This article, intended as a introdution to the other nuclear waste management papers in the journal, also briefly discusses the papers

Issues and scenarios for nuclear waste management systems analysis

International Nuclear Information System (INIS)

Mendel, J.E.

1980-11-01

The Planning and Analysis Branch of the Department of Energy's Nuclear Waste Management Programs is developing a new systems integration program. The Pacific Northwest Laboratory was requested to perform a brief scoping analysis of what scenarios, questions, and issues should be addressed by the systems integration program. This document reports on that scoping analysis

Disposal of radioactive wastes

International Nuclear Information System (INIS)

Dlouhy, Z.

1982-01-01

This book provides information on the origin, characteristics and methods of processing of radioactive wastes, as well as the philosophy and practice of their storage and disposal. Chapters are devoted to the following topics: radioactive wastes, characteristics of radioactive wastes, processing liquid and solid radioactive wastes, processing wastes from spent fuel reprocessing, processing gaseous radioactive wastes, fixation of radioactive concentrates, solidification of high-level radioactive wastes, use of radioactive wastes as raw material, radioactive waste disposal, transport of radioactive wastes and economic problems of radioactive wastes disposal. (C.F.)

Physicochemical aspects of extraction of uranium concentrate from the wastes and thermodynamic characteristics of thorium-uranium compounds

International Nuclear Information System (INIS)

Khamidov, F.A.

2017-01-01

The purpose of present work is elaboration of physicochemical aspects of extraction of uranium concentrate from the wastes and study of thermodynamic characteristics of thorium-uranium compounds. Therefore, the radiological monitoring of tailing dumps of Tajikistan has been conducted; the obtaining of uranium concentrate from the tailing dumps of uranium production has been studied; the obtaining of uranium concentrate from the tailing dumps of uranium production with application of local sorbents has been studied as well; thermal stability and thermodynamic characteristics of uranium-thorium compounds has been investigated; the flowsheets of extraction of uranium concentrate from the wastes have been elaborated.

DOE Office of Civilian Radioactive Waste Management (OCRWM) system studies digest

International Nuclear Information System (INIS)

McLeod, N.B.; Nguyen, T.D.; Drexelius, R.; McKee, R.W.

1992-06-01

The Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) has sponsored system studies to support the evaluation of alternative configurations and operations for the Civilian Radioactive Waste Management System (CRWMS) and the development of system requirements and design specifications. These studies are generally directed toward evaluating the impacts of alternatives to the monitored retrievable storage (MRS) and fuel rod consolidation, waste form and characteristics sequences, cask and canister concepts, allocation of waste acceptance rights, and system throughput rates. The objectives of this document are: To present major system issues and related system element issues in a structured manner; to discuss key results of major system studies and explain the basis for certain current system assumptions; to summarize the scope and results of completed system studies that are still relevant at the time this document is published; and to provide the background needed for identifying and prioritizing system issues to be resolved. Consistent with the objectives, the document does not include low-level subsystem studies addressing system element issues that do not interact with overall system issues. The document is expected to be updated as major new system studies are completed and significant new results are available

Proposed goals for radioactive waste management

International Nuclear Information System (INIS)

Bishop, W.P.; Frazier, D.H.; Hoos, I.R.; McGrath, P.E.; Metlay, D.S.; Stoneman, W.C.; Watson, R.A.

1977-04-01

Goals are proposed for the national radioactive waste management program to establish a policy basis for the guidance and coordination of the activities of government, business, and academic organizations whose responsibility it will be to manage radioactive wastes. The report is based on findings, interpretations, and analyses of selected primary literature and interviews of personnel concerned with waste management. Public concerns are identified, their relevance assessed, and a conceptual framework is developed that facilitates understanding of the dimensions and demands of the radioactive waste management problem. The nature and scope of the study are described along with the approach used to arrive at a set of goals appropriately focused on waste management

Quality assurance program description: Hanford Waste Vitrification Plant, Part 1

International Nuclear Information System (INIS)

1992-01-01

This document describes the Department of Energy's Richland Field Office (DOE-RL) quality assurance (QA) program for the processing of high-level waste as well as the Vitrification Project Quality Assurance Program for the design and construction of the Hanford Waste Vitrification Plant (HWVP). It also identifies and describes the planned activities that constitute the required quality assurance program for the HWVP. This program applies to the broad scope of quality-affecting activities associated with the overall HWVP Facility. Quality-affecting activities include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, maintaining, repairing, and modifying. Also included are the development, qualification, and production of waste forms which may be safely used to dispose of high-level radioactive waste resulting from national defense activities. The HWVP QA program is made up of many constituent programs that are being implemented by the participating organizations. This Quality Assurance program description is intended to outline and define the scope and application of the major programs that make up the HWVP QA program. It provides a means by which the overall program can be managed and directed to achieve its objectives. Subsequent parts of this description will identify the program's objectives, its scope, application, and structure

Radioactive waste management profiles. A compilation of data from the Net Enabled Waste Management Database (NEWMDB). No. 6, November 2004 (last updated 2004.12.16)

International Nuclear Information System (INIS)

2005-03-01

This Radioactive Waste Management Profiles report is a compilation of data collected by the Net Enabled Waste Management Database (NEWDB) from March to July 2004. The report contains information on national radioactive waste management programmes, plans and activities, relevant laws and regulations, policies and radioactive waste inventories. It provides or references details of the scope of NEWMDB data collections and it explains the formats of individual NEWMDB report pages

Construction and Demolition Waste Characteristics in Tanzania ...

African Journals Online (AJOL)

The construction industry generates a lot of construction and demolition (C&D) waste which puts some challenges to its management. For example, currently, in many towns in Tanzania, there are no landfill sites for solid waste disposal; and as a consequence open air dumping sites are used. Dumping C&D waste puts ...

Waste Transfer Leaks Control Decision Record

International Nuclear Information System (INIS)

RYAN, G.W.

2000-01-01

Control decision meetings for Waste Transfer Leaks were held on April 24,25,26, and 27, 2000. The agenda for the control decision meetings is included in Appendix A, and attendee lists are included in Appendix B. The purpose of the control decision meetings was to review and revise previously selected controls for the prevention or mitigation of waste transfer leak accidents. Re-evaluation of the controls is warranted due to revisions in the hazard and accident analysis for these Tank Farm events. In particular, calculated radiological consequences are significantly reduced from those currently reported in the Final Safety Analysis Report (FSAR). Revised hazard and accident analysis and a revised control recommendation will be reflected in an Authorization Basis Amendment to be submitted at the Department of Energy, Office of River Protection's (ORP's) request by June 30, 2000 to satisfy ORP Performance Incentive (PI) 2.1.1, Revision 1, ''Authorization Basis Management Process Efficiency Improvement''. The scope of the control decision meetings was to address all waste transfer leak-related hazardous conditions identified in the Tank Farm hazard analysis database, excluding those associated with the use of the Replacement Cross-Site Transfer System (RCSTS) slurry line and sluicing of Tank 241-C-106, which is addressed in FSAR Addendum 1. The scope of this control decision process does include future waste feed delivery waste transfer operations

Characteristics of medical waste in Malaysia

International Nuclear Information System (INIS)

Anwar Johari; Mutahharah, M.M.; Abdul, A.; Kalantarifard, A.; Rozainee, M.

2010-01-01

The main purpose for the waste characterization is to provide the data necessary to design a new extension of the existing medical waste incinerator plant in Perak. Medical waste from the existing medical waste incinerator was categorized into several components through a sorting process. Proximate analysis was conducted to determine its moisture content, volatile matter contents, ash and fixed carbon contents. Ultimate analysis was also conducted for the determination of carbon, hydrogen, oxygen, nitrogen and sulphur contents. The characterization study was conducted on site and for duration of 7 days. Result showed that the average total plastics (rigid and film) was 38 wt%. The rest of the composition comprised of mixed paper, surgery dress, diapers, absorbents and gloves with weight percents of 10%, 3%, 18%, 18% and 13% respectively. The average moisture content of the individual waste was 19.3%, 3%, 61.4%, 30.7%, 13.8% and 53.5 % for mixed paper, plastics, diaper, surgery dress, glove and absorbent respectively. The average volatile matter was 71.3%, 87.5%, 32.2%, 65.1%, 65.1%, 78.5% and 41.0% for individual waste. The average ash content was 2.1%, 0.7%, 2.6%, 0.5%, 6.5% and 0.8% for mixed paper, plastics, diaper, surgery dress, glove and absorbent respectively. The average fixed carbon was determined at 7.3%, 8.8%, 3.8%, 3.7%, 1.2% and 4.7% for mixed paper, plastics, diaper, surgery dress, glove and absorbent respectively. The average carbon, hydrogen, oxygen, nitrogen and sulphur contents are 51.8%, 8.6%, 35.5%, 0.3% and less than 0.1 respectively. The average calorific value (dry basis) was 27 MJ/ kg. (author)

Sources, amounts, and characteristics of low-level radioactive solid wastes

International Nuclear Information System (INIS)

Kibbey, A.H.; Godbee, H.W.

1979-01-01

Low-level radioactive solid wastes (LLW) are generated in the nuclear fuel cycle, national defense programs, institutional (especially medical/biological) applications, and other research and development activities. The estimated total accumulation of defense LLW, approx. 50.8 x 10 6 ft 3 (approx. 1.4 x 10 6 m 3 ), is roughly three times that estimated for commercial LLW, mill tailings excepted. All nuclear fuel cycle steps generate some LLW, but power plants are the chief source. From 1975 through 1977, reactor process stream cleanup generated approx. 1 x 10 6 (approx. 2.8 x 10 4 m 3 ) annually. Spent fuel storage (or reprocessing) and facility decontamination and decommissioning will become important LLW generators as the nuclear power industry matures. The LLW contains dry contaminated trash, much of which is combustible and/or compactible; discarded tools and equipment; wet filter sludges and ion-exchange resins; disposable filter cartridges; and solidified or sorbed liquids, including some organics. A distinguishing characteristic of LLW is a long-lived alpha-emitting transuranic content of 5 ft 3 (approx. 2.1 x 10 4 m 3 )/y. The majority of these wastes, > 6 x 10 5 ft 3 (> 1.7 x 10 4 m 3 ), was medical and academic wastes which usually contained isotopes with induced activities of less than or equal to 60-day half-life, neglecting 3 H and 14 C

Tank waste remediation system retrieval and disposal mission initial updated baseline summary

International Nuclear Information System (INIS)

Swita, W.R.

1998-01-01

This document provides a summary of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost), developed to demonstrate Readiness-to-Proceed (RTP) in support of the TWRS Phase 1B mission. This Updated Baseline is the proposed TWRS plan to execute and measure the mission work scope. This document and other supporting data demonstrate that the TWRS Project Hanford Management Contract (PHMC) team is prepared to fully support Phase 1B by executing the following scope, schedule, and cost baseline activities: Deliver the specified initial low-activity waste (LAW) and high-level waste (HLW) feed batches in a consistent, safe, and reliable manner to support private contractors' operations starting in June 2002; Deliver specified subsequent LAW and HLW feed batches during Phase 1B in a consistent, safe, and reliable manner; Provide for the interim storage of immobilized HLW (IHLW) products and the disposal of immobilized LAW (ILAW) products generated by the private contractors; Provide for disposal of byproduct wastes generated by the private contractors; and Provide the infrastructure to support construction and operations of the private contractors' facilities

Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1995-09-01

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions

Characteristics of spent fuel, high-level waste, and other radioactive wastes which may require long-term isolation

Energy Technology Data Exchange (ETDEWEB)

None

1987-12-01

The purpose of this report, and the information contained in the associated computerized data bases, is to establish the DOE/OCRWM reference characteristics of the radioactive waste materials that may be accepted by DOE for emplacement in the mined geologic disposal system. This report provides relevant technical data for use by DOE and its supporting contractors and is not intended to be a policy document. This document is backed up by five PC-compatible data bases, written in a user-oriented, menu-driven format, which were developed for this purpose. The data bases are the LWR Assemblies Data Base; the LWR Radiological Data Base; the LWR Quantities Data Base; the LWR NFA Hardware Data Base; and the High-Level Waste Data Base. The above data bases may be ordered using the included form. An introductory information diskette can be found inside the back cover of this report. It provides a brief introduction to each of these five PC data bases. 116 refs., 18 figs., 67 tabs.

Characteristics of spent fuel, high-level waste, and other radioactive wastes which may require long-term isolation

International Nuclear Information System (INIS)

1987-12-01

The purpose of this report, and the information contained in the associated computerized data bases, is to establish the DOE/OCRWM reference characteristics of the radioactive waste materials that may be accepted by DOE for emplacement in the mined geologic disposal system. This report provides relevant technical data for use by DOE and its supporting contractors and is not intended to be a policy document. This document is backed up by five PC-compatible data bases, written in a user-oriented, menu-driven format, which were developed for this purpose. The data bases are the LWR Assemblies Data Base; the LWR Radiological Data Base; the LWR Quantities Data Base; the LWR NFA Hardware Data Base; and the High-Level Waste Data Base. The above data bases may be ordered using the included form. An introductory information diskette can be found inside the back cover of this report. It provides a brief introduction to each of these five PC data bases. 116 refs., 18 figs., 67 tabs

Broadening GHG accounting with LCA: application to a waste management business unit.

Science.gov (United States)

Fallaha, Sophie; Martineau, Geneviève; Bécaert, Valérie; Margni, Manuele; Deschênes, Louise; Samson, Réjean; Aoustin, Emmanuelle

2009-11-01

In an effort to obtain the most accurate climate change impact assessment, greenhouse gas (GHG) accounting is evolving to include life-cycle thinking. This study (1) identifies similarities and key differences between GHG accounting and life-cycle assessment (LCA), (2) compares them on a consistent basis through a case study on a waste management business unit. First, GHG accounting is performed. According to the GHG Protocol, annual emissions are categorized into three scopes: direct GHG emissions (scope 1), indirect emissions related to electricity, heat and steam production (scope 2) and other indirect emissions (scope 3). The LCA is then structured into a comparable framework: each LCA process is disaggregated into these three scopes, the annual operating activities are assessed, and the environmental impacts are determined using the IMPACT2002+ method. By comparing these two approaches it is concluded that both LCA and GHG accounting provide similar climate change impact results as the same major GHG contributors are determined for scope 1 emissions. The emissions from scope 2 appear negligible whereas emissions from scope 3 cannot be neglected since they contribute to around 10% of the climate change impact of the waste management business unit. This statement is strengthened by the fact that scope 3 generates 75% of the resource use damage and 30% of the ecosystem quality damage categories. The study also shows that LCA can help in setting up the framework for a annual GHG accounting by determining the major climate change contributors.

Characteristics study of bentonite as candidate of buffer materials for radioactive waste disposal system

International Nuclear Information System (INIS)

Suryantoro; Arimuladi, S.P.; Sastrowardoyo, P.B.

1998-01-01

Literature studies on bentonite characteristic of, as candidate for radioactive waste disposal system, have been conducted. Several information have been obtained from references, which would be contributed on performance assessment of engineered barrier. The functions bentonite includes the buffering of chemical and physical behavior, i.e. swelling property, self sealing, hydraulic conductivities and gas permeability. This paper also presented long-term stability of bentonite in natural condition related to the illitisazation, which could change its buffering capacities. These information, showed that bentonite was satisfied to be used for candidate of buffer materials in radioactive waste disposal system. (author)

Mixed low-level waste form evaluation

International Nuclear Information System (INIS)

Pohl, P.I.; Cheng, Wu-Ching; Wheeler, T.; Waters, R.D.

1997-01-01

A scoping level evaluation of polyethylene encapsulation and vitreous waste forms for safe storage of mixed low-level waste was performed. Maximum permissible radionuclide concentrations were estimated for 15 indicator radionuclides disposed of at the Hanford and Savannah River sites with respect to protection of the groundwater and inadvertent intruder pathways. Nominal performance improvements of polyethylene and glass waste forms relative to grout are reported. These improvements in maximum permissible radionuclide concentrations depend strongly on the radionuclide of concern and pathway. Recommendations for future research include improving the current understanding of the performance of polymer waste forms, particularly macroencapsulation. To provide context to these estimates, the concentrations of radionuclides in treated DOE waste should be compared with the results of this study to determine required performance

Characteristics and management of infectious industrial waste in Taiwan

International Nuclear Information System (INIS)

Huang, M.-C.; Lin, Jim Juimin

2008-01-01

Infectious industrial waste management in Taiwan is based on the specific waste production unit. In other countries, management is based simply on whether the producer may lead to infectious disease. Thus, Taiwan has a more detailed classification of infectious waste. The advantage of this classification is that it is easy to identify the sources, while the disadvantage lies in the fact that it is not flexible and hence increases cost. This study presents an overview of current management practices for handling infectious industrial waste in Taiwan, and addresses the current waste disposal methods. The number of small clinics in Taiwan increased from 18,183 to 18,877 between 2003 and 2005. Analysis of the data between 2003 and 2005 showed that the majority of medical waste was general industrial waste, which accounted for 76.9%-79.4% of total medical waste. Infectious industrial waste accounted for 19.3%-21.9% of total medical waste. After the SARS event in Taiwan, the amount of infectious waste reached 19,350 tons in 2004, an increase over the previous year of 4000 tons. Waste minimization was a common consideration for all types of waste treatment. In this study, we summarize the percentage of plastic waste in flammable infectious industrial waste generated by medical units, which, in Taiwan was about 30%. The EPA and Taiwan Department of Health have actively promoted different recycling and waste reduction measures. However, the wide adoption of disposable materials made recycling and waste reduction difficult for some hospitals. It has been suggested that enhancing the education of and promoting communication between medical units and recycling industries must be implemented to prevent recyclable waste from entering the incinerator

Chemical and mechanical performance properties for various final waste forms -- PSPI scoping study

International Nuclear Information System (INIS)

Farnsworth, R.K.; Larsen, E.D.; Sears, J.W.; Eddy, T.L.; Anderson, G.L.

1996-09-01

The US DOE is obtaining data on the performance properties of the various final waste forms that may be chosen as primary treatment products for the alpha-contaminated low-level and transuranic waste at the INEL's Transuranic Storage Area. This report collects and compares selected properties that are key indicators of mechanical and chemical durability for Portland cement concrete, concrete formed under elevated temperature and pressure, sulfur polymer cement, borosilicate glass, and various forms of alumino-silicate glass, including in situ vitrification glass and various compositions of iron-enriched basalt (IEB) and iron-enriched basalt IV (IEB4). Compressive strength and impact resistance properties were used as performance indicators in comparative evaluation of the mechanical durability of each waste form, while various leachability data were used in comparative evaluation of each waste form's chemical durability. The vitrified waste forms were generally more durable than the non-vitrified waste forms, with the iron-enriched alumino-silicate glasses and glass/ceramics exhibiting the most favorable chemical and mechanical durabilities. It appears that the addition of zirconia and titania to IEB (forming IEB4) increases the leach resistance of the lanthanides. The large compositional ranges for IEB and IEB4 more easily accommodate the compositions of the waste stored at the INEL than does the composition of borosilicate glass. It appears, however, that the large potential variation in IEB and IEB4 compositions resulting from differing waste feed compositions can impact waste form durability. Further work is needed to determine the range of waste stream feed compositions and rates of waste form cooling that will result in acceptable and optimized IEB or IEB4 waste form performance. 43 refs

Calculation of projected waste loads for transuranic waste management alternatives

International Nuclear Information System (INIS)

Hong, K.; Kotek, T.; Koebnick, B.; Wang, Y.; Kaicher, C.

1995-01-01

The level of treatment and the treatment and interim storage site configurations (decentralized, regional, or centralized) impact transuranic (TRU) waste loads at and en route to sites in the US Department of Energy (DOE) complex. Other elements that impact waste loads are the volume and characteristics of the waste and the unit operation parameters of the technologies used to treat it. Projected annual complexwide TRU waste loads under various TRU waste management alternatives were calculated using the WASTEunderscoreMGMT computational model. WASTEunderscoreMGMT accepts as input three types of data: (1) the waste stream inventory volume, mass, and contaminant characteristics by generating site and waste stream category; (2) unit operation parameters of treatment technologies; and (3) waste management alternative definitions. Results indicate that the designed capacity of the Waste Isolation Pilot Plant, identified under all waste management alternatives as the permanent disposal facility for DOE-generated TRU waste, is sufficient for the projected complexwide TRU waste load under any of the alternatives

Tank waste remediation system retrieval authorization basis amendment task plan

International Nuclear Information System (INIS)

Goetz, T.G.

1998-01-01

This task plan is a documented agreement between Nuclear Safety and Licensing and the Process Development group within the Waste Feed Delivery organization. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Waste Delivery Program, Project W-211, and Project W-TBD

Waste Feed Evaporation Physical Properties Modeling

International Nuclear Information System (INIS)

Daniel, W.E.

2003-01-01

This document describes the waste feed evaporator modeling work done in the Waste Feed Evaporation and Physical Properties Modeling test specification and in support of the Hanford River Protection Project (RPP) Waste Treatment Plant (WTP) project. A private database (ZEOLITE) was developed and used in this work in order to include the behavior of aluminosilicates such a NAS-gel in the OLI/ESP simulations, in addition to the development of the mathematical models. Mathematical models were developed that describe certain physical properties in the Hanford RPP-WTP waste feed evaporator process (FEP). In particular, models were developed for the feed stream to the first ultra-filtration step characterizing its heat capacity, thermal conductivity, and viscosity, as well as the density of the evaporator contents. The scope of the task was expanded to include the volume reduction factor across the waste feed evaporator (total evaporator feed volume/evaporator bottoms volume). All the physical properties were modeled as functions of the waste feed composition, temperature, and the high level waste recycle volumetric flow rate relative to that of the waste feed. The goal for the mathematical models was to predict the physical property to predicted simulation value. The simulation model approximating the FEP process used to develop the correlations was relatively complex, and not possible to duplicate within the scope of the bench scale evaporation experiments. Therefore, simulants were made of 13 design points (a subset of the points used in the model fits) using the compositions of the ultra-filtration feed streams as predicted by the simulation model. The chemistry and physical properties of the supernate (the modeled stream) as predicted by the simulation were compared with the analytical results of experimental simulant work as a method of validating the simulation software

Can optical diagnosis of small colon polyps be accurate? Comparing standard scope without narrow banding to high definition scope with narrow banding.

Science.gov (United States)

Ashktorab, Hassan; Etaati, Firoozeh; Rezaeean, Farahnaz; Nouraie, Mehdi; Paydar, Mansour; Namin, Hassan Hassanzadeh; Sanderson, Andrew; Begum, Rehana; Alkhalloufi, Kawtar; Brim, Hassan; Laiyemo, Adeyinka O

2016-07-28

To study the accuracy of using high definition (HD) scope with narrow band imaging (NBI) vs standard white light colonoscope without NBI (ST), to predict the histology of the colon polyps, particularly those high definition colonoscopes with NBI. The histopathologic diagnosis was reported by pathologists as part of routine care. Of participants in the study, 55 (37%) were male and median (interquartile range) of age was 56 (19-80). Demographic, clinical characteristics, past medical history of patients, and the data obtained by two instruments were not significantly different and two methods detected similar number of polyps. In ST scope 89% of polyps were scope (P = 0.7). The ST scope had a positive predictive value (PPV) and positive likelihood ratio (PLR) of 86% and 4.0 for adenoma compared to 74% and 2.6 for HD scope. There was a trend of higher sensitivity for HD scope (68%) compare to ST scope (53%) with almost the same specificity. The ST scope had a PPV and PLR of 38% and 1.8 for hyperplastic polyp (HPP) compared to 42% and 2.2 for HD scope. The sensitivity and specificity of two instruments for HPP diagnosis were similar. Our results indicated that HD scope was more sensitive in diagnosis of adenoma than ST scope. Clinical diagnosis of HPP with either scope is less accurate compared to adenoma. Colonoscopy diagnosis is not yet fully matched with pathologic diagnosis of colon polyp. However with the advancement of both imaging and training, it may be possible to increase the sensitivity and specificity of the scopes and hence save money for eliminating time and the cost of Immunohistochemistry/pathology.

Assessment of selected furnace technologies for RWMC waste

International Nuclear Information System (INIS)

Batdorf, J.; Gillins, R.; Anderson, G.L.

1992-03-01

This report provides a description and initial evaluation of five selected thermal treatment (furnace) technologies, in support of earlier thermal technologies scoping work for application to the Idaho National Engineering Laboratory Radioactive Waste Management Complex (RWMC) buried wastes. The cyclone furnace, molten salt processor, microwave melter, ausmelt (fuel fired lance) furnace, and molten metal processor technologies are evaluated. A system description and brief development history are provided. The state of development of each technology is assessed, relative to treatment of RWMC buried waste

Immobilized low-level waste disposal options configuration study

International Nuclear Information System (INIS)

Mitchell, D.E.

1995-02-01

This report compiles information that supports the eventual conceptual and definitive design of a disposal facility for immobilized low-level waste. The report includes the results of a joint Westinghouse/Fluor Daniel Inc. evaluation of trade-offs for glass manufacturing and product (waste form) disposal. Though recommendations for the preferred manufacturing and disposal option for low-level waste are outside the scope of this document, relative ranking as applied to facility complexity, safety, remote operation concepts and ease of retrieval are addressed

Impact of vent pipe diameter on characteristics of waste degradation in semi-aerobic bioreactor landfill.

Science.gov (United States)

Jiang, Guobin; Liu, Dan; Chen, Weiming; Ye, Zhicheng; Liu, Hong; Li, Qibin

2017-10-01

The evolution mechanism of a vent pipe diameter on a waste-stabilization process in semi-aerobic bioreactor landfills was analyzed from the organic-matter concentration, biodegradability, spectral characteristics of dissolved organic matter, correlations and principal-component analysis. Waste samples were collected at different distances from the vent pipe and from different landfill layers in semi-aerobic bioreactor landfills with different vent pipe diameters. An increase in vent pipe diameter favored waste degradation. Waste degradation in landfills can be promoted slightly when the vent pipe diameter increases from 25 to 50 mm. It could be promoted significantly when the vent pipe diameter was increased to 75 mm. The vent pipe diameter is important in waste degradation in the middle layer of landfills. The dissolved organic matter in the waste is composed mainly of long-wave humus (humin), short-wave humus (fulvic acid) and tryptophan. The humification levels of the waste that was located at the center of vent pipes with 25-, 50- and 75-mm diameters were 2.2682, 4.0520 and 7.6419 Raman units, respectively. The appropriate vent pipe diameter for semi-aerobic bioreactor landfills with an 800-mm diameter was 75 mm. The effect of different vent pipe diameters on the degree of waste stabilization is reflected by two main components. Component 1 is related mainly to the content of fulvic acid, biologically degradable material and organic matter. Component 2 is related mainly to the content of tryptophan and humin from the higher vascular plants.

Factors Associated With Full Implementation of Scope of Practice.

Science.gov (United States)

Ganz, Freda DeKeyser; Toren, Orly; Fadlon, Yafit

2016-05-01

To describe whether nurses fully implement their scope of practice; nurses' perceptions of future practice implementation; and the association between scope of practice implementation with professional autonomy and self-efficacy. A descriptive correlational study was conducted using a convenience sample of 145 registered nurses with post-basic certification from two Israeli university hospitals, from May 2012 to September 2013. Five questionnaires were distributed: (a) Demographic and Work Characteristics, (b) Implementation of Scope of Practice, (c) Attitudes Towards Future Practice, (d) Practice Behavior Scale, and (e) Practice Self-Efficacy. Descriptive statistics for all demographic and questionnaire data were analyzed. Two regression models were developed, where current and future implementations were the criterion variables and demographic and work characteristics, professional autonomy, and self-efficacy were the predictors. High levels of professional autonomy, self-efficacy, and attitudes towards future practice were found in contrast to low or moderate levels of current implementation of the full extent of scope of practice. Primary reasons associated with low implementation were lack of relevance to practice and permission to perform the practice. Significant associations were found between professional autonomy, self-efficacy, and attitudes towards future practice, but not with current implementation. Nurses wanted to practice to the full extent of their scope of practice and felt able to do so but were hindered by administrative and not personal barriers. Even though staff nurses with post-basic certification had high levels of professional autonomy and self-efficacy, many were not implementing the full extent of their scope of practice. Similar to findings from around the world, external factors, such as administrative and policy barriers, were found to thwart the full implementation of nurses' full scope of practice. Therefore, practicing nurses

Industrial Special Wastes Generated in Iowa and Manpower Characteristics of Employee Handlers, Volume I.

Science.gov (United States)

Pierce, David R.

This document, Vol. I in a set, presents information obtained from a survey of industry in Iowa to determine the use and quantities, distribution, and treatment and disposal practices of hazardous waste generators. Additionally, it tabulated the number and manpower characteristics of employees who are in daily contact with such hazardous…

Survey of the geological characteristics on the Japanese Islands for disposal of RI and research institute waste

Energy Technology Data Exchange (ETDEWEB)

Hagiwara, Shigeru [Chuo Kaihatsu Co., Ltd., Tokyo (Japan); Sakamoto, Yoshiaki; Takebe, Shinichi; Ogawa, Hiromichi; Nakayama, Shinichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2002-12-01

In the disposal of radioactive wastes arising from radioisotope utilization facilities and nuclear research facilities, it is necessary to establish the disposal system in proportion to half-lives of radionuclides and radioactivity concentrations in the wastes. According to this disposal system, the radioactive waste should be buried in the underground near the surface, shallow position and deep position. Therefore, it is important to grasp the features of the earth scientific phenomena and geological structure for the disposal system of radioactive waste. Then, for the purpose of the survey of the geological characteristics around the Japanese Islands whole neighborhood, the earth scientific phenomena at present, the geological structure and geotectonic history were summarized on the basis of the existing literatures. (author)

Formation and filtration characteristics of solids generated in a high level liquid waste treatment process. Filtration characteristics of solids formed in simulated high level liquid waste

International Nuclear Information System (INIS)

Kondo, Y.; Kubota, M.

1997-01-01

The filtration characteristics of solids generated in a simulated high level liquid waste (HLLW) were experimentally examined, when the simulated HLLW was processed according to the ordinary way of actual HLLW treatment process. The filtration characteristics of solids depended on the particle size. The phosphomolybdic acid, which was very fine particle with about 0.1 μm diameter, made slurry a 'difficult-to-filter' slurry, if the phosphomolybdic acid content (wt%) to the whole solids in a slurry exceeded 50wt%. On the contrary, the zirconium compounds (zirconium molybdate and zirconium telluride) had positive effect on filtration characteristics because of their relatively large particle size of about 3 to 5 μm. When the zirconium compounds content was above 50 wt%, slurry became a 'easy-to-filter' slurry. A centrifugal sedimentation was discussed as a solid/liquid separation technique for very fine particles such as phosphomolybdic acid. The theoretical feed flow rate corresponded to 0.1 μm diameter particles was about 20 1/h at the centrifugal acceleration of about 8000 G. (author)

SRP decontamination and decommissioning scoping study

International Nuclear Information System (INIS)

Martin, W.P.

1986-06-01

Of the approximately 3000 site facilities, 496 were judged to be radioactively contaminated thereby requiring Decontamination and Decommissioning (D and D) after shutdown. To enable projection of D and D timing for each of the 496 facilities, a plant shutdown schedule was developed. A 5-year ''cool-down'' period was added to the highly contaminated facilities to allow radioactive decay resulting in a reduction of cost, waste volume, and radiation exposure. D and D of all facilities is projected to be completed in FY 2045. Since essentially all of the plant facilities are scheduled to operate past FY 2000, only seventy-four of the 496 facilities are projected to be decommissioned prior to FY 2000. These facilities include currently excessed facilities and those scheduled for shutdown in the near future - seepage basins, HWCTR, R-Reactor, high level waste tanks, etc. The type of D and D chosen is the factor having the most significant effect on D and D costs and waste volumes. The two types of final D and D are Entombment and Dismantlement. Dismantlement can increase costs and waste volumes by a factor of 2 to 100 compared to Entombment. This point should be kept in mind when reviewing this scoping study as approximately 75% of the projects are estimated based upon the less costly Entombment option. The D and D estimates for the 496 facilities are summarized by plant area in Table 3 and by custodian group (Program/General Department) in Table 4. The total estimated D and D cost in constant FY 1986 dollars is approximately $800,000,000, with total solid waste volumes of 5,000,000 and 170,000 cubic feet, for low level waste (LLW) and transuranic waste (TRU), respectively. A 6% annual escalation factor increases the total project costs of 800,000,000, FY 1986 dollars to 7 billion dollars. 27 refs

Household solid waste characteristics and management in Chittagong, Bangladesh

International Nuclear Information System (INIS)

Sujauddin, Mohammad; Huda, S.M.S.; Hoque, A.T.M. Rafiqul

2008-01-01

Solid waste management (SWM) is a multidimensional challenge faced by urban authorities, especially in developing countries like Bangladesh. We investigated per capita waste generation by residents, its composition, and the households' attitudes towards waste management at Rahman Nagar Residential Area, Chittagong, Bangladesh. The study involved a structured questionnaire and encompassed 75 households from five different socioeconomic groups (SEGs): low (LSEG), lower middle (LMSEG), middle (MSEG), upper middle (UMSEG) and high (HSEG). Wastes, collected from all of the groups of households, were segregated and weighed. Waste generation was 1.3 kg/household/day and 0.25 kg/person/day. Household solid waste (HSW) was comprised of nine categories of wastes with vegetable/food waste being the largest component (62%). Vegetable/food waste generation increased from the HSEG (47%) to the LSEG (88%). By weight, 66% of the waste was compostable in nature. The generation of HSW was positively correlated with family size (r xy = 0.236, p xy = 0.244, p xy = 0.671, p < 0.01) of the households. Municipal authorities are usually the responsible agencies for solid waste collection and disposal, but the magnitude of the problem is well beyond the ability of any municipal government to tackle. Hence dwellers were found to take the service from the local waste management initiative. Of the respondents, an impressive 44% were willing to pay US$0.3 to US$0.4 per month to waste collectors and it is recommended that service charge be based on the volume of waste generated by households. Almost a quarter (22.7%) of the respondents preferred 12-1 pm as the time period for their waste to be collected. This study adequately shows that household solid waste can be converted from burden to resource through segregation at the source, since people are aware of their role in this direction provided a mechanism to assist them in this pursuit exists and the burden is distributed according to the

Tank waste remediation system retrieval and disposal mission initial updated baseline summary

International Nuclear Information System (INIS)

Swita, W.R.

1998-01-01

This document provides a summary of the proposed Tank Waste Remediation System Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost) developed to demonstrate the Tank Waste Remediation System contractor's Readiness-to-Proceed in support of the Phase 1B mission

Effects of stabilizers on the heat transfer characteristics of a nuclear waste canister

International Nuclear Information System (INIS)

Vafai, K.; Ettefagh, J.

1986-07-01

This report summarizes the feasibility and the effectiveness of using stabilizers (internal metal structural components) to augment the heat transfer characteristics of a nuclear waste canister. The problem was modeled as a transient two-dimensional heat transfer in two physical domains - the stabilizer and the wedge (a 30-degree-angle canister segment), which includes the heat-producing spent-fuel rods. This problem is solved by a simultaneous and interrelated numerical investigation of the two domains in cartesian and polar coordinate systems. The numerical investigations were performed for three cases. In the first case, conduction was assumed to be the dominant mechanism for heat transfer. The second case assumed that radiation was the dominant mechanism, and in the third case both radiation and conduction were considered as mechanisms of heat transfer. The results show that for typical conditions in a waste package design, the stabilizers are quite effective in reducing the overall temperature in a waste canister. Furthermore, the results show that increasing the stabilizer thickness over the thickness specified in the present design has a negligible effect on the temperature distribution in the canister. Finally, the presence of the stabilizers was found to shift the location of the peak temperature areas in the waste canister

Radioactive waste management

International Nuclear Information System (INIS)

1982-07-01

In response to the Sixth Report of the Royal Commission on Environmental Pollution, a White Paper was published in 1977, announcing a number of steps to deal with the problems presented by wastes from the nuclear industry and setting out the position of the then government. The present White paper is in four sections. i. A brief description of the nature of radioactive wastes, and the general objectives of waste management. ii. What has been achieved, the role of the Radioactive Waste Management Advisory Committee, the expansion of research, and the conclusions from the review of existing controls. iii. The present position for each major category of waste, including relevant current action and research, transport and decommissioning. iv. The next steps. Research and development must continue; shallow land burial and the carefully controlled disposal of certain wastes to the sea will continue to play a role; and, for some wastes, new disposal facilities are needed at an early date. For others, the appropriate course of action at the moment is properly controlled storage. New developments are also required in organisation. Throughout, the public must be kept fully informed about what is being done, and there must be proper scope for public discussion. (U.K.)

Characterization of urban waste management practices in developing Asian countries: A new analytical framework based on waste characteristics and urban dimension.

Science.gov (United States)

Aleluia, João; Ferrão, Paulo

2016-12-01

, despite some common characteristics shared among cities in developing Asia, their specific circumstances can significantly vary, even within the same country, calling for the need for context-specific waste management approaches. Set against this background, this paper proposes a guiding framework in the form of a matrix that maps out approaches observed in the management of municipal solid waste in cities of developing Asian countries as a function of the city dimension, share of organics on waste streams, and wealth generated by the city. The cities of Surabaya (Indonesia), Bangalore (India), Quy Nhon (Viet Nam), and Matale (Sri Lanka) are showcased as good practices in the region in the management of solid waste, with their experiences used to illustrate the framework laid out in the matrix. Copyright © 2016 Elsevier Ltd. All rights reserved.

WASTE PACKAGE TRANSPORTER DESIGN

International Nuclear Information System (INIS)

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

1998-01-01

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

EIA scoping in England and Wales: Practitioner approaches, perspectives and constraints

International Nuclear Information System (INIS)

Wood, Graham; Glasson, John; Becker, Julia

2006-01-01

Scoping plays a critical role in shaping the nature and extent of the environmental information subsequently contained in an Environmental Impact Statement (EIS), yet it has been identified as an area of weakness in practice () and remains a poorly understood and under-researched component of EIA. This paper provides a detailed empirical investigation and assessment of recent scoping activity in England and Wales, in the context of evolving European Union (EU) regulations. Conceptual and contextual issues associated with scoping are outlined prior to the presentation of key findings, including: approaches to scoping; the assessment of significance; characteristics and influence of consultation; and perceived constraints to scoping. The paper concludes with an overview of findings, possible explanatory factors, and recommendations for future practice

Scoping erosion flow loop test results in support of Hanford WTP

International Nuclear Information System (INIS)

Duignan, M.; Imrich, K.; Fowley, M.; Restivo, M.; Reigel, M.

2015-01-01

The Waste Treatment and Immobilization Plant (WTP) will process Hanford Site tank waste by converting the waste into a stable glass form. Before the tank waste can be vitrified, the baseline plan is to process the waste through the Pretreatment (PT) Facility where it will be mixed in various process vessels using Pulse Jet Mixers (PJM) and transferred to the High Level Waste (HLW) or Low Activity Waste (LAW) vitrification facilities. The Department of Energy (DOE) and Defense Nuclear Facility Safety Board (DNFSB), as well as independent review groups, have raised concerns regarding the design basis for piping erosion in the PT Facility. Due to the complex nature of slurry erosion/corrosion wear and the unique conditions that exist within the PT Facility, additional testing has been recommended by these entities. Pipe loop testing is necessary to analyze the potential for localized wear at elbows and bends, close the outstanding PT and HLW erosion/corrosion technical issues, and underpin BNI's design basis for a 40-year operational life for black cell piping and vessels. SRNL is consulting with the DOE Office of River Protection (ORP) to resolve technical concerns related to piping erosion/corrosion (wear) design basis for PT. SRNL was tasked by ORP to start designing, building, and testing a flow loop to obtain long-term total-wear rate data using bounding simulant chemistry, operating conditions, and prototypical materials. The initial test involved a scoping paint loop to locate experimentally the potential high-wear locations. This information will provide a basis for the placement of the many sensitive wear measurement instruments in the appropriate locations so that the principal flow-loop test has the best chance to estimate long-term erosion and corrosion. It is important to note that the scoping paint loop test only utilized a bounding erosion simulant for this test. A full chemical simulant needs to be added for the complete test flow loop. The

Airborne radionuclide waste-management reference document

International Nuclear Information System (INIS)

Brown, R.A.; Christian, J.D.; Thomas, T.R.

1983-07-01

This report provides the detailed data required to develop a strategy for airborne radioactive waste management by the Department of Energy (DOE). The airborne radioactive materials of primary concern are tritium (H-3), carbon-14 (C-14), krypton-85 (Kr-85), iodine-129 (I-129), and radioactive particulate matter. The introductory section of the report describes the nature and broad objectives of airborne waste management. The relationship of airborne waste management to other waste management programs is described. The scope of the strategy is defined by considering all potential sources of airborne radionuclides and technologies available for their management. Responsibilities of the regulatory agencies are discussed. Section 2 of this document deals primarily with projected inventories, potential releases, and dose commitments of the principal airborne wastes from the light water reactor (LWR) fuel cycle. In Section 3, dose commitments, technologies, costs, regulations, and waste management criteria are analyzed. Section 4 defines goals and objectives for airborne waste management

A quick system for estimating the purification performance of waste water treatment plants based on the macroscopic and microscopic characteristics of activated sludge; Sistema rapido de estimacion de los rendimientos en depuracion de una EDAR en funcion de las caracteristicas macroscopicas del fango activado

Energy Technology Data Exchange (ETDEWEB)

Jimenez, C.; Fernandez, N.; Horra de la, J. M.; Rodriguez, E.; Isac, L.; Salas, D.; Gomez, E.; Ortiz Vargas, A.; Gonzalez Carballo, J. A.

2001-07-01

Microbiological studies of activated sludge require time, specialized staff and the arduous task of identifying and analysing the results, which is not usually within the scope of every laboratory. This article raises the possibility of carrying out a simplified study of active sludge, based on its macroscopic and microscopic characteristics, which produces a sludge index value that is directly related to the percentage reduction of solids in suspension, COD and BOD in the waste water treatment plant. In addition, this sludge index would also provide the possibility of quickly obtaining a historical record of biological quality values using a simple protocol that could be use for comparisons. (Author) 10 refs.

DOE Waste Treatability Group Guidance

International Nuclear Information System (INIS)

Kirkpatrick, T.D.

1995-01-01

This guidance presents a method and definitions for aggregating U.S. Department of Energy (DOE) waste into streams and treatability groups based on characteristic parameters that influence waste management technology needs. Adaptable to all DOE waste types (i.e., radioactive waste, hazardous waste, mixed waste, sanitary waste), the guidance establishes categories and definitions that reflect variations within the radiological, matrix (e.g., bulk physical/chemical form), and regulated contaminant characteristics of DOE waste. Beginning at the waste container level, the guidance presents a logical approach to implementing the characteristic parameter categories as part of the basis for defining waste streams and as the sole basis for assigning streams to treatability groups. Implementation of this guidance at each DOE site will facilitate the development of technically defined, site-specific waste stream data sets to support waste management planning and reporting activities. Consistent implementation at all of the sites will enable aggregation of the site-specific waste stream data sets into comparable national data sets to support these activities at a DOE complex-wide level

DOE Waste Treatability Group Guidance

Energy Technology Data Exchange (ETDEWEB)

Kirkpatrick, T.D.

1995-01-01

This guidance presents a method and definitions for aggregating U.S. Department of Energy (DOE) waste into streams and treatability groups based on characteristic parameters that influence waste management technology needs. Adaptable to all DOE waste types (i.e., radioactive waste, hazardous waste, mixed waste, sanitary waste), the guidance establishes categories and definitions that reflect variations within the radiological, matrix (e.g., bulk physical/chemical form), and regulated contaminant characteristics of DOE waste. Beginning at the waste container level, the guidance presents a logical approach to implementing the characteristic parameter categories as part of the basis for defining waste streams and as the sole basis for assigning streams to treatability groups. Implementation of this guidance at each DOE site will facilitate the development of technically defined, site-specific waste stream data sets to support waste management planning and reporting activities. Consistent implementation at all of the sites will enable aggregation of the site-specific waste stream data sets into comparable national data sets to support these activities at a DOE complex-wide level.

Manitoba Hazardous Waste Management Corporation system scope and technology study

Energy Technology Data Exchange (ETDEWEB)

1988-01-01

The Manitoba Hazardous Waste Management Corporation is charged with the responsibility of implementing a hazardous waste management system in the province. A review was undertaken of the planning work performed to date and of the Corporation's development strategy. The evaluation was based on a review of the literature and on experience with hazardous waste planning, management, and engineering. To facilitate evaluation, the development strategies were visualized as made up of 3 logical components: the mechanisms or business vehicles used; the rates of development employed; and the geographical locations in which the activities take place. Based on ownership or funding source, 3 business development options were identified: public corporation, private enterprise, and joint venture. The only two options possible in terms of rate of development are incremental and immediate. Three general locations were considered; in Manitoba, outside Manitoba, or a combination of both. Results showed that a joint venture is a good option since it offers a good tradeoff to minimize expenditures between public and private financing, and it enables combining the flexibility and freedom of action of a private corporation with the responsibility of a public corporation. The incremental approach provides more flexibility than immediate development and is the most practical solution to the many uncertainties of the hazardous waste problem. This approach is nominally more costly because it takes longer and cannot capitalize on economies of scale, but it also minimizes the risk of making the wrong capital investment and is therefore a safer investment approach. 108 refs., 28 figs., 15 tabs.

Manitoba Hazardous Waste Management Corporation system scope and technology study

Energy Technology Data Exchange (ETDEWEB)

1988-01-01

The Manitoba Hazardous Waste Management Corporation is charged with the responsibility of implementing a hazardous waste management system in the province. A review was undertaken of the planning work performed to date and of the Corporation's development strategy. The evaluation was based on a review of the literature and on experience with hazardous waste planning, management, and engineering. To facilitate evaluation, the development strategies were visualized as made up of 3 logical components: the mechanisms or business vehicles used; the rates of development employed; and the geographical locations in which the activities take place. Based on ownership or funding source, 3 business development options were identified: public corporation, private enterprise, and joint venture. The only two options possible in terms of rate of development are incremental and immediate. Only 3 general locations were considered: in Manitoba, outside Manitoba, or a combination of both. Results showed that a joint venture is a good option since it offers a good tradeoff to minimize expenditures between public and private financing, and it enables combining the flexibility and freedom of action of a private corporation with the responsibility of a public corporation. The incremental approach provides more flexibility than immediate development and is the most practical solution to the many uncertainties of the hazardous waste problem. This approach is nominally more costly because it takes longer and cannot capitalize on economies of scale, but it also minimizes the risk of making the wrong capital investment and is therefore a safer investment approach. 105 refs. 28 figs., 15 tabs.

Shale disposal of U.S. high-level radioactive waste.

Energy Technology Data Exchange (ETDEWEB)

Sassani, David Carl; Stone, Charles Michael; Hansen, Francis D.; Hardin, Ernest L.; Dewers, Thomas A.; Martinez, Mario J.; Rechard, Robert Paul; Sobolik, Steven Ronald; Freeze, Geoffrey A.; Cygan, Randall Timothy; Gaither, Katherine N.; Holland, John Francis; Brady, Patrick Vane

2010-05-01

This report evaluates the feasibility of high-level radioactive waste disposal in shale within the United States. The U.S. has many possible clay/shale/argillite basins with positive attributes for permanent disposal. Similar geologic formations have been extensively studied by international programs with largely positive results, over significant ranges of the most important material characteristics including permeability, rheology, and sorptive potential. This report is enabled by the advanced work of the international community to establish functional and operational requirements for disposal of a range of waste forms in shale media. We develop scoping performance analyses, based on the applicable features, events, and processes identified by international investigators, to support a generic conclusion regarding post-closure safety. Requisite assumptions for these analyses include waste characteristics, disposal concepts, and important properties of the geologic formation. We then apply lessons learned from Sandia experience on the Waste Isolation Pilot Project and the Yucca Mountain Project to develop a disposal strategy should a shale repository be considered as an alternative disposal pathway in the U.S. Disposal of high-level radioactive waste in suitable shale formations is attractive because the material is essentially impermeable and self-sealing, conditions are chemically reducing, and sorption tends to prevent radionuclide transport. Vertically and laterally extensive shale and clay formations exist in multiple locations in the contiguous 48 states. Thermal-hydrologic-mechanical calculations indicate that temperatures near emplaced waste packages can be maintained below boiling and will decay to within a few degrees of the ambient temperature within a few decades (or longer depending on the waste form). Construction effects, ventilation, and the thermal pulse will lead to clay dehydration and deformation, confined to an excavation disturbed zone within

Electricity generation from food wastes and characteristics of organic matters in microbial fuel cell.

Science.gov (United States)

Li, Hui; Tian, Yu; Zuo, Wei; Zhang, Jun; Pan, Xiaoyue; Li, Lipin; Su, Xinying

2016-04-01

The microbial fuel cell (MFC) was evaluated as an alternative way to recover electricity from canteen based food waste. Characteristics of the organics in food waste before and after the MFC treatment were analyzed to investigate how the organic matters were biodegraded and transformed during the MFC treatment. A maximum power density of 5.6W/m(3) and an average output voltage of 0.51V were obtained. During the MFC operation, the hydrophilic and acidic fractions were more readily degraded, compared to the neutral fractions. Additionally, aromatic compounds in the hydrophilic fraction were more preferentially removed than non-aromatic compounds. The MFC could easily remove the tryptophan protein-like substances in all fractions and aromatic proteins in hydrophilic and hydrophobic neutral fractions. Additionally, the hydrophobic amide-1 proteins and aliphatic components were readily hydrolyzed and biodegraded in the MFC. These findings may facilitate the pretreatment and posttreatment choices for MFC system fed with food waste. Copyright © 2016 Elsevier Ltd. All rights reserved.

Time evolution of the general characteristics and Cu retention capacity in an acid soil amended with a bentonite winery waste

DEFF Research Database (Denmark)

Fernandez Calviño, David; Rodríguez-Salgado, Isabel; Pérez-Rodríguez, Paula

2015-01-01

The effect of bentonite waste added to a "poor" soil on its general characteristic and copper adsorption capacity was assessed. The soil was amended with different bentonite waste concentrations (0, 10, 20, 40 and 80Mgha-1) in laboratory pots, and different times of incubation of samples were tes...

Latest developments in the predisposal of radioactive waste at the radioactive waste management department from ifin-hh

International Nuclear Information System (INIS)

Dragolici, F.; Dogaru, G.; Neacsu, E.

2016-01-01

The Radioactive Waste Management Department (DMDR) from IFIN-HH has a wide experience in the management of the non-fuel cycle radioactive wastes from all over Romania generated from nuclear techniques and technologies application, assuring the radiological safety and security of operators, population and environment. During 2011-2015 was implemented a major upgrading programme applied both on the technological systems of the building and on equipment. The paper describes the facility developments having the scope to share to the public and stakeholders the radioactive waste predisposal capabilities available at DMDR-IFIN-HH. As a whole, today DMDR-IFIN-HH represents a complete and complex infrastructure, assuring high quality services in all the steps related to the management of the institutional radioactive waste in Romania. (authors)

Characteristics of solidified high-level waste products

International Nuclear Information System (INIS)

1979-01-01

The object of the report is to contribute to the establishment of a data bank for future preparation of codes of practice and standards for the management of high-level wastes. The work currently in progress on measuring the properties of solidified high-level wastes is being studied

Waste classification sampling plan

International Nuclear Information System (INIS)

Landsman, S.D.

1998-01-01

The purpose of this sampling is to explain the method used to collect and analyze data necessary to verify and/or determine the radionuclide content of the B-Cell decontamination and decommissioning waste stream so that the correct waste classification for the waste stream can be made, and to collect samples for studies of decontamination methods that could be used to remove fixed contamination present on the waste. The scope of this plan is to establish the technical basis for collecting samples and compiling quantitative data on the radioactive constituents present in waste generated during deactivation activities in B-Cell. Sampling and radioisotopic analysis will be performed on the fixed layers of contamination present on structural material and internal surfaces of process piping and tanks. In addition, dose rate measurements on existing waste material will be performed to determine the fraction of dose rate attributable to both removable and fixed contamination. Samples will also be collected to support studies of decontamination methods that are effective in removing the fixed contamination present on the waste. Sampling performed under this plan will meet criteria established in BNF-2596, Data Quality Objectives for the B-Cell Waste Stream Classification Sampling, J. M. Barnett, May 1998

Hanford/Rocky Flats collaboration on development of supercritical carbon dioxide extraction to treat mixed waste

International Nuclear Information System (INIS)

Hendrickson, D.W.; Biyani, R.K.; Brown, C.M.; Teter, W.L.

1995-11-01

Proposals for demonstration work under the Department of Energy's Mixed Waste Focus Area, during the 1996 through 1997 fiscal years included two applications of supercritical carbon dioxide to mixed waste pretreatment. These proposals included task RF15MW58 of Rocky Flats and task RL46MW59 of Hanford. Analysis of compatibilities in wastes and work scopes yielded an expectation of substantial collaboration between sites whereby Hanford waste streams may undergo demonstration testing at Rocky Flats, thereby eliminating the need for test facilities at Hanford. This form of collaboration is premised the continued deployment at Rocky Flats and the capability for Hanford samples to be treated at Rocky Flats. The recent creation of a thermal treatment contract for a facility near Hanford may alleviate the need to conduct organic extraction upon Rocky Flats wastes by providing a cost effective thermal treatment alternative, however, some waste streams at Hanford will continue to require organic extraction. Final site waste stream treatment locations are not within the scope of this document

Hanford/Rocky Flats collaboration on development of supercritical carbon dioxide extraction to treat mixed waste

Energy Technology Data Exchange (ETDEWEB)

Hendrickson, D.W.; Biyani, R.K. [Westinghouse Hanford Co., Richland, WA (United States); Brown, C.M.; Teter, W.L. [Kaiser-Hill Co., Golden, CO (United States)

1995-11-01

Proposals for demonstration work under the Department of Energy`s Mixed Waste Focus Area, during the 1996 through 1997 fiscal years included two applications of supercritical carbon dioxide to mixed waste pretreatment. These proposals included task RF15MW58 of Rocky Flats and task RL46MW59 of Hanford. Analysis of compatibilities in wastes and work scopes yielded an expectation of substantial collaboration between sites whereby Hanford waste streams may undergo demonstration testing at Rocky Flats, thereby eliminating the need for test facilities at Hanford. This form of collaboration is premised the continued deployment at Rocky Flats and the capability for Hanford samples to be treated at Rocky Flats. The recent creation of a thermal treatment contract for a facility near Hanford may alleviate the need to conduct organic extraction upon Rocky Flats wastes by providing a cost effective thermal treatment alternative, however, some waste streams at Hanford will continue to require organic extraction. Final site waste stream treatment locations are not within the scope of this document.

Commercial Spent Nuclear Fuel Waste Package Misload Analysis

International Nuclear Information System (INIS)

J.K. Knudson

2003-01-01

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

Waste biomass toward hydrogen fuel supply chain management for electricity: Malaysia perspective

Science.gov (United States)

Zakaria, Izatul Husna; Ibrahim, Jafni Azhan; Othman, Abdul Aziz

2016-08-01

Green energy is becoming an important aspect of every country in the world toward energy security by reducing dependence on fossil fuel import and enhancing better life quality by living in the healthy environment. This conceptual paper is an approach toward determining physical flow's characteristic of waste wood biomass in high scale plantation toward producing gas fuel for electricity using gasification technique. The scope of this study is supply chain management of syngas fuel from wood waste biomass using direct gasification conversion technology. Literature review on energy security, Malaysia's energy mix, Biomass SCM and technology. This paper uses the theoretical framework of a model of transportation (Lumsden, 2006) and the function of the terminal (Hulten, 1997) for research purpose. To incorporate biomass unique properties, Biomass Element Life Cycle Analysis (BELCA) which is a novel technique develop to understand the behaviour of biomass supply. Theoretical framework used to answer the research questions are Supply Chain Operations Reference (SCOR) framework and Sustainable strategy development in supply chain management framework

Utilizing waste materials to enhance mechanical and durability characteristics of concrete incorporated with silica fume

Directory of Open Access Journals (Sweden)

Hamza Ali

2017-01-01

Full Text Available Construction and demolition wastes are increasing significantly due to augmented boom of modern construction. Although the partial cement replacement materials do promote the idea of sustainable construction, the use of construction and demolition waste can also be considered to be viable option to advance the sustainability in modern construction practices. This paper investigates the use of industrial waste materials namely marble dust and crushed bricks as replacement of natural fine aggregates along with the use of silica fume as a partial cement replacement on the mechanical properties and durability characteristics of concrete. Partial replacement levels of waste materials were 10 and 20 percent by volume while the partial replacement level of silica fume was kept to 20 percent at all concrete samples. The results reported in this paper show that the use of marble dust as a replacement material to the natural fine aggregates resulted in an increase in the mechanical properties of concrete. However, the use of crushed bricks did not substantially contribute in the development of strength. Water permeability of concrete incorporated with both silica fume and waste materials (marble dust and crushed bricks decreased significantly. The decrease in water permeability of concrete was attributed to the pozzolanic reaction of silica fume with calcium hydroxide of cement and the filler effect of the waste materials of marble dust and crushed bricks. The use of waste materials also enhance the freeze and thaw resistance of concrete. Authors strongly suggest that the pozzolanic reaction and the development of the microstructure of the concrete through the use of waste materials are largely responsible from the advances in the durability of concrete.

Characteristics of Cement Solidification of Metal Hydroxide Waste

Directory of Open Access Journals (Sweden)

Dae-Seo Koo

2017-02-01

Full Text Available To perform the permanent disposal of metal hydroxide waste from electro-kinetic decontamination, it is necessary to secure the technology for its solidification. The integrity tests on the fabricated solidification should also meet the criteria of the Korea Radioactive Waste Agency. We carried out the solidification of metal hydroxide waste using cement solidification. The integrity tests such as the compressive strength, immersion, leach, and irradiation tests on the fabricated cement solidifications were performed. It was also confirmed that these requirements of the criteria of Korea Radioactive Waste Agency on these cement solidifications were met. The microstructures of all the cement solidifications were analyzed and discussed.

Characteristics of cement solidification of metal hydroxide waste

Energy Technology Data Exchange (ETDEWEB)

Koo, Dae Seo; Sung, Hyun Hee; Kim, Seung Soo; Kim, Gye Nam; Choi, Jong Won [Dept. of Decontemination Decommission Technology Development, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2017-02-15

To perform the permanent disposal of metal hydroxide waste from electro-kinetic decontamination, it is necessary to secure the technology for its solidification. The integrity tests on the fabricated solidification should also meet the criteria of the Korea Radioactive Waste Agency. We carried out the solidification of metal hydroxide waste using cement solidification. The integrity tests such as the compressive strength, immersion, leach, and irradiation tests on the fabricated cement solidifications were performed. It was also confirmed that these requirements of the criteria of Korea Radioactive Waste Agency on these cement solidifications were met. The microstructures of all the cement solidifications were analyzed and discussed.

CONRRAD portal : 'Knowledge management tool for radioactive waste'

International Nuclear Information System (INIS)

Gomiz, Pablo R.; Vetere, Claudia L.

2009-01-01

The scope of this paper deals with the development and implementation of a software system aimed at improving the Knowledge Management System in the Argentine Nuclear Waste Program and includes the necessary considerations for its success. (author)

WASTE MANAGEMENT AT SRS - MAKING IT HAPPEN

International Nuclear Information System (INIS)

Heenan, T. F.; Kelly, S.

2002-01-01

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

Integrated data base report - 1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1997-12-01

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions

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

International Nuclear Information System (INIS)

Beam, T.G.

1994-11-01

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

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

Energy Technology Data Exchange (ETDEWEB)

Beam, T.G.

1994-11-01

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

Safeguards on nuclear waste

International Nuclear Information System (INIS)

Crawford, D.W.

1995-01-01

Safeguards and security policies within the Department of Energy (DOE) have been implemented in a graded fashion for the protection, control and accountability of nuclear materials. This graded philosophy has meant that safeguards on low-equity nuclear materials, typically considered of low diversion attractiveness such as waste, has been relegated to minimal controls. This philosophy has been and remains today an acceptable approach for the planning and implementation of safeguards on this material. Nuclear waste protection policy and guidance have been issued due to a lack of clear policy and guidance on the identification and implementation of safeguards controls on waste. However, there are issues related to safe-guarding waste that need to be clarified. These issues primarily stem from increased budgetary and resource pressures to remove materials from safeguards. Finally, there may be an unclear understanding, as to the scope and content of vulnerability assessments required prior to terminating safeguards on waste and other discardable materials and where the authority should lie within the Department for making decisions regarding safeguards termination. This paper examines these issues and the technical basis for Departmental policy for terminating safeguards on waste

WASTE PACKAGE TRANSPORTER DESIGN

Energy Technology Data Exchange (ETDEWEB)

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

1998-09-23

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

Investigation on the characteristics of liquid wastes depending on their generation sources and study on optimum treatment method

Energy Technology Data Exchange (ETDEWEB)

Kim, Sang Guk; Kim, Dong Chan; Shin, Dae Hyun; Son, Seung Geun; Roh, Nam Sun; Woo, Je Kyung [Korea Inst. of Energy Research, Taejon (Korea, Republic of)

1995-12-01

The major research contents conducted this year are as follows: (1) environmental regulation with respect to the treatment of the liquid waste in the U.S.A., (2) the present status of the generation and treatment of liquid wastes for large producers(>1,000 ton/year), (3) analysis for heating value element, heavy metal content, halogenated species on collected samples, (4) investigation on estimation method of energy recovery rate from liquid waste, (5) design of a lab. scale reactor which could be capable of conducting thermal decomposition test with small quantity of sample. In this study, present status of liquid waste generation and treatment is investigated, and thermal decomposition characteristics are studied using a lab. scale thermal reactor. The purpose of this research is to divide liquid waste into groups and to present best treatment method for their each group. (author). 24 refs., 21 figs., 23 tabs.

40 CFR 22.37 - Supplemental rules governing administrative proceedings under the Solid Waste Disposal Act.

Science.gov (United States)

2010-07-01

... administrative proceedings under the Solid Waste Disposal Act. 22.37 Section 22.37 Protection of Environment... Supplemental rules governing administrative proceedings under the Solid Waste Disposal Act. (a) Scope. This... sections 3005(d) and (e), 3008, 9003 and 9006 of the Solid Waste Disposal Act (42 U.S.C. 6925(d) and (e...

Research needs in cement-based waste forms

International Nuclear Information System (INIS)

McDaniel, E.W.; Spence, R.D.; Tallent, O.K.

1990-01-01

Cement-based waste forms are one of the most widely used waste disposal options, yet definitive knowledge of the fate of the waste species inside the waste form is lacking. A fundamental understanding of the chemistry and microstructure of the waste forms would lead to a better understanding of the mass transfer of the waste species, more confidence in predicting and extrapolating waste form performance, and design of better waste forms. Better and cheaper leach tests would lead to quicker and more cost effective screening of waste form alternatives. In addition, assessment of durability may be important to predicting waste form performance in the field. It should be noted that the research needs discussed in this report are from the perspective of investigators working in applied waste management areas, while the proposed investigations are fundamental or basic. Details as to experimental methods and tools to be used in achieving the objectives of the proposed are research beyond the scope of this paper and are better filled in by others. In broad terms, the research topics discussed are correlation of cement-based waste form physical properties to performance, waste-form fundamental chemistry and microstructure, and product performance testing

Implementation Plan. Environmental Restoration and Waste Management Programmatic Environmental Impact Statement

Energy Technology Data Exchange (ETDEWEB)

1994-01-01

In accordance with the Department of Energy`s National Environmental Policy Act implementing procedures in Volume 10 of the Code of Federal Regulations, Section 1021,312, the Environmental Restoration and Waste Management Programmatic Environmental Impact Statement Implementation Plan has two primary purposes: to provide guidance for the preparation of the Programmatic Environmental Impact Statement and to record the issues resulting from the scoping and the extended public participation process. The Implementation Plan identifies and discusses the following: background of Environmental Restoration and Waste Management activities, the purpose of the Programmatic Environmental Impact Statement, and the relationship of the Programmatic Environmental Impact Statement to other Departmental initiatives (Chapter 1); need and purposes for action (Chapter 2); scoping process and results of the public participation program in defining the scope of the Programmatic Environmental Impact Statement, including a summary of the comments received and their disposition (Chapter 3); planned scope and content of the Programmatic Environmental Impact Statement (Chapter 4); consultations with other agencies and the role of cooperating agencies (Chapter 5); planned schedule of major Programmatic Environmental Impact Statement milestones (Chapter 6); and responsibilities for preparation of the Programmatic Environmental Impact Statement (Chapter 7).

The Sort on Radioactive Waste Type Model: A method to sort single-shell tanks into characteristics groups

International Nuclear Information System (INIS)

Hill, J.G.; Anderson, G.S.; Simpson, B.C.

1995-02-01

The Sort on Radioactive Waste Type (SORWT) Model is a method to categorize Hanford Site single-shell tanks (SSTS) into groups of tanks expected to exhibit similar chemical and physical characteristics based on their major waste types and processing histories. The model has identified 24 different waste-type groups encompassing 133 of the 149 SSTs and 93% of the total waste volume in SSTS. The remaining 16 SSTs and associated wastes could not be grouped. according to the established criteria and were placed in an ungrouped category. A detailed statistical verification study has been conducted that employs analysis of variance (ANOVA) and the core sample analysis data collected since 1989. These data cover eight tanks and five SORWT groups. The verification study showed that these five SORWT groups are highly statistically significant; they represent approximately 10% of the total waste volume and 26% of the total sludge volume in SSTS. Future sampling recommendations based on the SORWT Model results include 32 core samples from 16 tanks and 18 auger samples from six tanks. Combining these data with the existing body of information will form the basis for characterizing 98 SSTs (66%). These 98 SSTs represent 78% of the total waste volume, 61% of the total sludge volume, and 88 % of the salt cake volume

EASEWASTE-life cycle modeling capabilities for waste management technologies

DEFF Research Database (Denmark)

Bhander, Gurbakhash Singh; Christensen, Thomas Højlund; Hauschild, Michael Zwicky

2010-01-01

Background, Aims and Scope The management of municipal solid waste and the associated environmental impacts are subject of growing attention in industrialized countries. EU has recently strongly emphasized the role of LCA in its waste and resource strategies. The development of sustainable solid...... waste management systems applying a life-cycle perspective requires readily understandable tools for modelling the life cycle impacts of waste management systems. The aim of the paper is to demonstrate the structure, functionalities and LCA modelling capabilities of the PC-based life cycle oriented...... waste management model EASEWASTE, developed at the Technical University of Denmark specifically to meet the needs of the waste system developer with the objective to evaluate the environmental performance of the various elements of existing or proposed solid waste management systems. Materials...

Melting characteristics of a plasma torch melter according to the waste feeding method

International Nuclear Information System (INIS)

Kim, T. W.; Choi, J. R.; Park, S. C.; Lu, C. S.; Park, J. K.; Hwang, T. W.; Shin, S. W.

2001-01-01

By using a batch type plasma torch melting system, continuous feeding and melting tests of non-combustible waste were executed. Using the results, the establishment of a heat transfer model and its verification were executed; the characteristics of the molten slag, exhaust gas, fly dust, volatilization of Cs, and leaching of slag were analyzed. In order to establish the heat transfer mode, the followings were considered; the electrical energy supplied to the plasma torch, the absorbed energy to the plasma torch for generating the plasma gas, the absorbed energy to the cooling water of the plasma torch, the energy supplied to the melter from the plasma gas by radiant heat, the energy loss through the exhaust gas, the waste melting energy, and the heating energy of an inner crucible and the melter. The concrete and soil were melted for the verification of the model. The waste was fed through waste feeder by the amount of 0.5kg or 1kg that was calculated by using the model. The experiment for the verification resulted in that the model was fitted well until the melter was heated sufficiently. If the electrical energy of 128kW were supplied to the plasma torch, energy balance of the plasma melting system was calculated with the model: the absorbed energy to the plasma torch for generating the plasma gas (27kW), the absorbed energy to the cooling water of the plasma torch (0∼ 36kW), the energy loss through the exhaust gas (5 ∼ 8kW), the waste melting energy (14kW), and the heating energy of an inner crucible and the melter (82 ∼ 43kW)

Greater confinement disposal of radioactive wastes

International Nuclear Information System (INIS)

Trevorrow, L.E.; Gilbert, T.L.; Luner, C.; Merry-Libby, P.A.; Meshkov, N.K.; Yu, C.

1985-01-01

Low-level radioactive waste (LLW) includes a broad spectrum of different radionuclide concentrations, half-lives, and hazards. Standard shallow-land burial practice can provide adequate protection of public health and safety for most LLW. A small volume fraction (approx. 1%) containing most of the activity inventory (approx. 90%) requires specific measures known as greater-confinement disposal (GCD). Different site characteristics and different waste characteristics - such as high radionuclide concentrations, long radionuclide half-lives, high radionuclide mobility, and physical or chemical characteristics that present exceptional hazards - lead to different GCD facility design requirements. Facility design alternatives considered for GCD include the augered shaft, deep trench, engineered structure, hydrofracture, improved waste form, and high-integrity container. Selection of an appropriate design must also consider the interplay between basic risk limits for protection of public health and safety, performance characteristics and objectives, costs, waste-acceptance criteria, waste characteristics, and site characteristics

Activity monitoring of alpha-bearing wastes

International Nuclear Information System (INIS)

Birkhoff, G.; Bondar, L.

1980-01-01

The paper aims at the survey on the actual situation in activity monitoring of alpha-bearing wastes. Homogeneous materials such as liquid-, gaseous- and homogeneous solid wastes are amenable to destructive analyses of representative samples. Available destructive analyses methods are sensitive and precise enough to cope with all requirements in alpha-waste monitoring. The more difficult problems are encountered with alpha-contaminated solids, when representative sampling is not practicable. Non-destructive analysis techniques are applied for monitoring this category of solid wastes. The techniques for nondestructive analysis of alpha-bearing wastes are based on the detection of gamma and/or neutron-emission of actinides. Principles and a theory of non-destructive radiometric assay of plutonium contaminated solid waste streams are explained. Guidelines for the calibration of instruments and interpretation of experimental data are given. Current theoretical and experimental development work in this problem area is reviewed. Evaluations concerning capabilities and limitations of monitoring systems for alpha-bearing solid wastes are very complex and out of the scope of this paper

Naval Waste Package Design Sensitivity

International Nuclear Information System (INIS)

T. Schmitt

2006-01-01

The purpose of this calculation is to determine the sensitivity of the structural response of the Naval waste packages to varying inner cavity dimensions when subjected to a comer drop and tip-over from elevated surface. This calculation will also determine the sensitivity of the structural response of the Naval waste packages to the upper bound of the naval canister masses. The scope of this document is limited to reporting the calculation results in terms of through-wall stress intensities in the outer corrosion barrier. This calculation is intended for use in support of the preliminary design activities for the license application design of the Naval waste package. It examines the effects of small changes between the naval canister and the inner vessel, and in these dimensions, the Naval Long waste package and Naval Short waste package are similar. Therefore, only the Naval Long waste package is used in this calculation and is based on the proposed potential designs presented by the drawings and sketches in References 2.1.10 to 2.1.17 and 2.1.20. All conclusions are valid for both the Naval Long and Naval Short waste packages

Gideaa study site. Scope of activities and main results

International Nuclear Information System (INIS)

Ahlbom, K.; Andersson, J.E.; Nordqvist, R.; Ljunggren, C.; Tiren, S.; Voss, C.

1991-10-01

During the period from 1977-1986 SKB (Swedish Nuclear Fuel and Waste Management Co) performed surface and borehole investigations of 14 study sites for the purpose of assessing their suitability for a repository of spent nuclear fuel. The next phase in the SKB site selection programme will be to perform detailed characterization, including characterization from shafts and/or tunnels, of two or three sites. The detailed investigations will continue over several years to provide all the data needed for a licensing application to build a repository. Such an application is foreseen to be given to the authorities around the year 2003. It is presently not clear if anyone of the study sites will be selected as a site for detailed characterization. Other site with geological and/or socio-economical characteristics judged more favourable may very well be the ones selected. However, as a part of the background documentation needed for the site selection studies to come, summary reports will be prepared for most study sites. These reports will include scope of activities, main results, uncertainties and need of complementary investigations. This report concerns the Gideaa study site. (au)

Kamlunge study site. Scope of activities and main results

International Nuclear Information System (INIS)

Ahlbom, K.; Andersson, J.E.; Andersson, P.; Ittner, T.; Tiren, S.; Ljunggren, C.

1992-05-01

During the period from 1977-1986 SKB (Swedish nuclear Fuel and Waste Management Co.) performed surface and borehole investigations of 14 study sites for the purpose of assessing their suitability for a repository of spent nuclear fuel. The next phase in the SKB site selection programme will be to perform detailed characterization, including characterization from shafts and/or tunnels, of two or three sites. The detailed investigations will continue over several years to provide all the data needed for a licensing application to build a repository. Such an application is foreseen to be given to the authorities around the year 2003. It is presently not clear if anyone of the study sites will be selected as a site for detailed characterization. Other sites with geological and/or socio-economical characteristics judged more favourable may very well be selected. However, as a part of the background documentation needed for the site selection studies to come, summary reports will be prepared for most study sites. These reports will include scope of activities, main results, uncertainties and need of complementary investigations. This report concerns the Kamlunge study site. (79 refs.) (au)

Fjaellveden study site. Scope of activities and main results

International Nuclear Information System (INIS)

Ahlbom, K.; Andersson, J.E.; Nordqvist, R.; Ljunggren, C.; Tiren, S.; Voss, C.

1991-10-01

During the period from 1977-1986 SKB (Swedish Nuclear Fuel and Waste Management CO) performed surface and borehole investigations of 14 study sites for the purpose of assessing their suitability for a repository of spent nuclear fuel. The next phase in the SKB site selection programme will be to perform detailed characterization, including characterization from shafts and/or tunnels, of two or three sites. The detailed investigations will continue over several years to provide all the data needed for a licensing application to build repository. Such an application is foreseen to be given to the authorities around the year 2003. It is presently not clear if anyone of the study sites will be selected as a site for detailed characterization. Other sites with geological and/or socio-economical characteristics judged more favourable may very well be the ones selected. However, as a part of the background documentation needed for the site selection studies to come, summary reports will be prepared for most study sites. These reports will include scope of activities, main results, uncertainties and need for complementary investigations. This report concerns the Fjaellveden study site. (au)

Integrated data base report--1995: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1996-12-01

The information in this report summarizes the U.S. Department of Energy (DOE) data base for inventories, projections, and characteristics of domestic spent nuclear fuel and radioactive waste. This report is updated annually to keep abreast of continual waste inventory and projection changes in both the government and commercial sectors. Baseline information is provided for DOE program planning purposes and to support DOE program decisions. Although the primary purpose of this document is to provide background information for program planning within the DOE community, it has also been found useful by state and local governments, the academic community, and some private citizens

Defense waste solidification studies. Volume 2. Drawing supplement. Savannah River Plant, Project S-1780

International Nuclear Information System (INIS)

1977-01-01

Volume 2 contains the drawings prepared and used in scoping and estimating the Glass-Form Waste Solidification facilities and the alternative studies cited in the report, the Off-Site Shipping Case, the Decontaminated Salt Storage Case, and a revised Reference Plant (Concrete-Form Waste) Case

Characteristics of low-level radioactive waste disposed during 1987--1989

International Nuclear Information System (INIS)

Roles, G.W.

1990-12-01

This report presents the volume, activity, and radionuclide distributions in low-level radioactive waste (LLW) disposed during 1987 through 1989 at the commercial disposal facilities located near Barnwell, SC, Richland, WA, and Beatty, NV. The report has been entirely assembled from descriptions of waste provided in LLW shipment manifests. Individual radionuclide distributions are listed as a function of waste class, of general industry, and of waste stream. In addition, information is presented about disposal of wastes containing chelating agents, about use of solidification media, about the distribution of radiation levels at the surfaces of waste containers, and about the distribution of waste container sizes. Considerably more information is presented about waste disposed at the Richland and Beatty disposal facilities than at the Barnwell disposal facility

Characteristics of transuranic waste at Department of Energy sites

International Nuclear Information System (INIS)

Jensen, R.T.; Wilkinson, F.J. III.

1983-05-01

This document reports data and information on TRU waste from all DOE generating and storage sites. The geographical location of the sites is shown graphically. There are four major sections in this document. The first three cover the TRU waste groups known as Newly Generated, Stored, and Buried Wastes. Subsections are included under Newly Generated and Stored on contact-handled and remote-handled waste. These classifications of waste are defined, and the current or expected totals of each are given. Figure 1.3 shows the total amount of Buried and Stored TRU waste. Preparation of this document began in 1981, and most of the data are as of December 31, 1980. In a few cases data were reported to December 31, 1981, and these have been noted. The projections in the Newly Generated section were made, for the most part, at the end of 1981

The characteristics of household food waste in Hong Kong and their implications for sewage quality and energy recovery.

Science.gov (United States)

Zan, Feixiang; Dai, Ji; Hong, Yuze; Wong, Meiyin; Jiang, Feng; Chen, Guanghao

2018-04-01

Food waste (FW) is a worldwide environmental issue due to its huge production amount. FW separation from municipal solid waste followed by different treatment strategies has been widely accepted. Food waste disposer (FWD) is a promising approach to separate and collect household food waste (HFW), which has been widely applied in many countries. However, the feasibility of FWD application in many countries is still being debated due to the major concerns over the impact of FWD on the wastewater treatment plants. In order to investigate the feasibility of FWD application, FW characterization is a key work to be conducted in advance. Since the FW characteristics largely vary by region, reliable and representative FW characteristics in different countries should be investigated. To provide such information for further studies on FW management for Hong Kong, HFW was collected from Hong Kong typical households over one year and analyzed systemically in this study. The FW composition varied little from place to place or season to season, and the values observed were comparable with results reported from other countries and regions. Based on the reliable HFW characteristics obtained from one-year survey coupled with statistical analysis, simulated HFW for Hong Kong consisting of 50% fruits, 20% vegetables, 20% starchy food and 10% meat was proposed for future studies. On the other hand, the FWD treatment caused more than 50% of the biodegradable organic content in HFW to dissolve. With a ratio of 1 g food waste to 1 L sewage, total solids in the wastewater stream were predicted to increase by 73%, total chemical oxygen demand by 61%, soluble chemical oxygen demand by 110%, nitrogen by 6% and phosphorus by 16%. Theoretically, 22 million m 3 /year of additional methane could be generated if 50% of Hong Kong residential buildings equipped with FWD. That would certainly increase pollutant loading on the wastewater treatment plants, but also energy recovery potential

Current Issues and Situation of Producer Responsibility in Waste Management in Indonesia

Directory of Open Access Journals (Sweden)

Antonius Priyo Nugroho Sulami

2017-11-01

Full Text Available Producer responsibility for wastes has been encouraged in Indonesia since 2008. The Ministry of Environment of the Republic of Indonesia also promoted the reduce, reuse, and recycle (3R concept using the community-based approach of waste banks integrated with the extended producer responsibility (EPR concept. However, related research and implementation are still limited. This study aims to identify the challenges of fulfilling producer responsibility in waste management and determine whether the integration concept could generate outcomes expected from the EPR concept. A semi-structured interview survey of several stakeholders from the government, industrial, and waste management sectors was conducted and the data generated was used to simulate an integration scheme using a system dynamics approach. Secondary data and information from Bandung municipality were used as input for the simulation. The interview survey found that the concerns and issues of fulfilling producer responsibility in waste management include lack of awareness, unavailability of clear guidelines, and the limited capacity of the current recycling sector. The results of the simulation suggested that if the integration scheme is applied, each business entity might bear the responsibility of IDR 29.4 million per year and 14.7 tons of waste per year for the scope of four sectors and IDR 34.1 million per year and 17 tons of waste per year for the scope of two sectors.

Category 2 and 4 investigation-derived waste readiness evaluation plan

International Nuclear Information System (INIS)

Ludowise, J.D.

1996-08-01

This Readiness Evaluation Plan presents the methodology used to assess the readiness for loading investigation-derived waste drums on trucks for transport to the Environmental Restoration Disposal Facility. The scope of this plan includes an assessment of the organizations, procedures, and regulatory approvals necessary for the handling of investigation-derived waste containers and the subsequent transportation of materials to the Environmental Restoration Disposal Facility

Hanford Waste Tank Bump Accident and Consequence Analysis

International Nuclear Information System (INIS)

BRATZEL, D.R.

2000-01-01

This report provides a new evaluation of the Hanford tank bump accident analysis and consequences for incorporation into the Authorization Basis. The analysis scope is for the safe storage of waste in its current configuration in single-shell and double-shell tanks

In situ vitrification on buried waste

International Nuclear Information System (INIS)

Bates, S.O.

1992-01-01

In situ vitrification (ISV) is being evaluated as a remedial treatment technology for buried mixed and transuranic (TRU) wastes at the Subsurface Disposal Area (SDA) at Idaho National Engineering Laboratory (INEL) and can be related to buried wastes at other Department of Energy (DOE) sites. There are numerous locations around the DOE Complex where wastes were buried in the ground or stored for future burial. The Buried Waste Program (BWP) is conducting a comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) remedial investigation/feasibility study (RI/FS) for the Department of Energy - Field Office Idaho (DOE-ID). As part of the RI/FS, an ISV scoping study on the treatability of the SDA mixed low-level and mixed TRU waste is being performed for applicability to remediation of the waste at the Radioactive Waste Management Complex (RWMC). The ISV project being conducted at the INEL by EG ampersand G Idaho, Inc. consists of a treatability investigation to collect data to satisfy nine CERCLA criteria with regards to the SDA. This treatability investigation involves a series of experiments and related efforts to study the feasibility of ISV for remediation of mixed and TRU waste disposed of at the SDA

WRAP Module 1 waste characterization plan

International Nuclear Information System (INIS)

Mayancsik, B.A.

1995-01-01

The purpose of this document is to present the characterization methodology for waste generated, processed, or otherwise the responsibility of the Waste Receiving and Processing (WRAP) Module 1 facility. The scope of this document includes all solid low level waste (LLW), transuranic (TRU), mixed waste (MW), and dangerous waste. This document is not meant to be all-inclusive of the waste processed or generated within WRAP Module 1, but to present a methodology for characterization. As other streams are identified, the method of characterization will be consistent with the other streams identified in this plan. The WRAP Module 1 facility is located in the 200 West Area of the Hanford Site. The facility's function is two-fold. The first is to verify/characterize, treat and repackage contact handled (CH) waste currently in retrievable storage in the LLW Burial Grounds, Hanford Central Waste Complex, and the Transuranic Storage and Assay Facility (TRUSAF). The second is to verify newly generated CH TRU waste and LLW, including MW. The WRAP Module 1 facility provides NDE and NDA of the waste for both drums and boxes. The NDE is used to identify the physical contents of the waste containers to support waste characterization and processing, verification, or certification. The NDA results determine the radioactive content and distribution of the waste

Waste heat utilization in agriculture

International Nuclear Information System (INIS)

Horacek, P.

1983-01-01

The Proceedings contain 17 papers presented at meetings of the Working Group for Waste Heat Utilization of the Committee of the European Society of Nuclear Methods in Agriculture of which 7 fall under the INIS scope. The working group met in May 1980 in Brno, Czechoslovakia, in October 1981 in Aberdeen, Scotland and in September 1982 in Brno. (Z.M.)

Hanford facility dangerous waste permit application, 616 Nonradioactive dangerous waste storage facility

International Nuclear Information System (INIS)

Price, S.M.

1997-01-01

This chapter provides information on the physical, chemical, and biological characteristics of the waste stored at the 616 NRDWSF. A waste analysis plan is included that describes the methodology used for determining waste types

Hanford facility dangerous waste permit application, 616 Nonradioactive dangerous waste storage facility

Energy Technology Data Exchange (ETDEWEB)

Price, S.M.

1997-04-30

This chapter provides information on the physical, chemical, and biological characteristics of the waste stored at the 616 NRDWSF. A waste analysis plan is included that describes the methodology used for determining waste types.

Food Waste Drivers in Europe, from Identification to Possible Interventions

Directory of Open Access Journals (Sweden)

Massimo Canali

2016-12-01

Full Text Available The growing volumes of food globally lost or wasted and implications for food security and sustainability have raised the concern of researchers, governments, international organizations and grass-root movements. Much research and experiences investigating food waste causes and drivers focus on one specific segment of the food supply chain and limit the analysis to the situation of one or few countries, while the few studies of wider geographical scope also target other relevant and diversified objectives (e.g., food waste definition, quantification, environmental and economic impacts, and recommendations for interventions. This study, carried out by a network of European institutions involved in research and initiatives against food waste, focuses on the analysis of a broad area, Europe, through a wide and systematic literature review and consultation with stakeholders in international focus groups. The food supply chain was divided into seven segments and three main contexts were defined for the examination of food waste sources: Technological, Institutional (related to organisational factors, i.e., business management, economy, legislation, and policy, and Social (related to consumers’ behaviours and lifestyles. Results suggest a wide and multifaceted problem, interconnected across all stages of the food supply chain, from primary production, to final consumption. Within each context, the identified drivers have been grouped according to the possibilities and the type of interventions for food waste reduction. A final cross-contextual prioritization distinguished food waste sources related to (A inherent characteristics of food; (B social and economic factors; (C individual non-readily changeable behaviours; (D other priorities targeted by private and public stakeholders; (E diversified factors, such as mismanagement, inefficient legislation, lack of awareness or information; and sub-optimal use of available technologies, which could be

Utilization of mining and mineral wastes

Energy Technology Data Exchange (ETDEWEB)

Park, Kyung Ho; Hong, Seung Woong; Choi, Young Yoon; Kim, Byung Gyu; Park, Je Shin [Korea Institute of Geology Mining and Materials, Taejon (Korea)

1998-12-01

Up to now, it is estimated that more than 50 million tons of mineral wastes have been generated mining industries and deposited on the land in Korea. Much of cultivated land and hilly areas have been occupied by this wastes, which cause pollution of the environment. Utilization of the mineral wastes is preferable to stabilization because full use would both eliminate the waste and broaden the mineral resource base. Therefore, the development of utilization techniques of mineral wastes is very important not only for improving the environment but also for resource conservation. In countries with high population and poor natural resources like Korea, the utilization of these wastes is essential to decrease the environmental problem and the secure the resources and the study on this field play a important part. Therefore, the objective of this study is to develop the utilization techniques of the mineral wastes. In first year's research, the contents and scope of this study are 1) Present condition and Field Survey on the mineral wastes with respect of their utilization, 2) Reviews of Current effects and research to utilize mineral wastes, 3) Characterization of mineral wastes and environmental test, 4) Evaluation and study on the utilization. (author). 67 refs., 25 tabs., 54 figs.

Utilization of mining and mineral wastes

Energy Technology Data Exchange (ETDEWEB)

Park, Kyung Ho; Hong, Seung Woong; Choi, Young Yoon; Kim, Byung Gyu; Park, Je Shin [Korea Institute of Geology Mining and Materials, Taejon (Korea)

1998-12-01

Up to now, it is estimated that more than 50 million tons of mineral wastes have been generated mining industries and deposited on the land in Korea. Much of cultivated land and hilly areas have been occupied by this wastes, which cause pollution of the environment. Utilization of the mineral wastes is preferable to stabilization because full use would both eliminate the waste and broaden the mineral resource base. Therefore, the development of utilization techniques of mineral wastes is very important not only for improving the environment but also for resource conservation. In countries with high population and poor natural resources like Korea, the utilization of these wastes is essential to decrease the environmental problem and the secure the resources and the study on this field play a important part. Therefore, the objective of this study is to develop the utilization techniques of the mineral wastes. In first year's research, the contents and scope of this study are 1) Present condition and Field Survey on the mineral wastes with respect of their utilization, 2) Reviews of Current effects and research to utilize mineral wastes, 3) Characterization of mineral wastes and environmental test, 4) Evaluation and study on the utilization. (author). 67 refs., 25 tabs., 54 figs.

Comparative techniques for nuclear fuel cycle waste management systems

International Nuclear Information System (INIS)

Pelto, P.J.; Voss, J.W.

1979-09-01

A safety assessment approach for the evaluation of predisposal waste management systems is described and applied to selected facilities in the light water reactor (LWR) once-through fuel cycle and a potential coprocessed UO 2 -PuO 2 fuel cycle. This approach includes a scoping analysis on pretreatment waste streams and a more detailed analysis on proposed waste management processes. The primary evaluation parameters used in this study include radiation exposures to the public from radionuclide releases from normal operations and potential accidents, occupational radiation exposure from normal operations, and capital and operating costs. On an overall basis, the waste management aspects of the two fuel cycles examined are quite similar. On an individual facility basis, the fuel coprocessing plant has the largest waste management impact

Review on waste inventory, waste characteristics and candidate site for LLW disposal in Thailand

International Nuclear Information System (INIS)

Yamkate, P.; Sriyotha, P.; Punnachaiya, M.; Danladkaew, K.

1997-01-01

It is a worldwide practice that radioactive waste has to be kept under control to be ensured of low potential impact on man and his environment. In Thailand, the OAEP is responsible for all radioactive waste management activities, both operation and the competent authority. The radioactive waste in Thailand consists of low level wastes from the application of radioisotopes in medical treatment and industry, the operation of the 2 MW TRIGA Mark III Research Reactor and the production of radioisotopes at OAEP. A plan for central disposal site has been set up. The near surface disposal method is chosen for this aspect because of its simple, inexpensive and adequate safe and very well know process. 8 refs., 6 tabs

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

Factors associated with emergency medical services scope of practice for acute cardiovascular events.

Science.gov (United States)

Williams, Ishmael; Valderrama, Amy L; Bolton, Patricia; Greek, April; Greer, Sophia; Patterson, Davis G; Zhang, Zefeng

2012-01-01

To examine prehospital emergency medical services (EMS) scope of practice for acute cardiovascular events and characteristics that may affect scope of practice; and to describe variations in EMS scope of practice for these events and the characteristics associated with that variability. In 2008, we conducted a telephone survey of 1,939 eligible EMS providers in nine states to measure EMS agency characteristics, medical director involvement, and 18 interventions authorized for prehospital care of acute cardiovascular events by three levels of emergency medical technician (EMT) personnel. A total of 1,292 providers responded to the survey, for a response rate of 67%. EMS scope of practice interventions varied by EMT personnel level, with the proportion of authorized interventions increasing as expected from EMT-Basic to EMT-Paramedic. Seven of eight statistically significant associations indicated that EMS agencies in urban settings were less likely to authorize interventions (odds ratios department-based EMS agencies were two to three times more likely to authorize interventions for EMT-Intermediate personnel. Volunteer EMS agencies were more than twice as likely as nonvolunteer agencies to authorize interventions for EMT-Basic and EMT-Intermediate personnel but were less likely to authorize any one of the 11 interventions for EMT-Paramedics. Greater medical director involvement was associated with greater likelihood of authorization of seven of the 18 interventions for EMT-Basic and EMT-Paramedic personnel but had no association with EMT-Intermediate personnel. We noted statistically significant variations in scope of practice by rural vs. urban setting, medical director involvement, and type of EMS service (fire department-based/non-fire department-based; volunteer/paid). These variations highlight local differences in the composition and capacity of EMS providers and offer important information for the transition towards the implementation of a national scope of

Proposed goals for radioactive waste management

International Nuclear Information System (INIS)

Bishop, W.P.; Hoos, I.R.; McGrath, P.E.; Metlay, D.S.; Stoneman, W.C.

1978-05-01

A special, seven member, interdisciplinary task group of consultants was established in January 1976 to propose goals for the national waste management program. This is the report of that group. The proposed goals are intended as a basis for the NRC to establish a policy by which to guide and coordinate the activities of government, business, and academic organizations whose responsibility it will be to manage radioactive wastes. The report is based on findings, interpretations and analysis by the authors who examined selected primary literature and interviewed many individuals concerned with waste management. The authors extended the scope of their inquiry and proposed goals to cover 'all technical and societal aspects necessary to an operating waste management system, rather than dealing with the regulatory process alone.' The waste management goals as developed are simple statements of principles which appear to the authors to be important conditions to insure the proper establishment and operation of a system to manage radioactive wastes.' In brief, the goals are designed to protect people and things of value in an equitable manner

Development of radionuclide inventory estimation method using scaling factor for the Korean NPPs: scope and status

International Nuclear Information System (INIS)

Hwang, Ki Ha; Lee, Sang Chul; Kang, Sang Hee; Lee, Kun Jai; Jeong, Chan Woo; Ahn, Sang Myeon; Kim, Tae Wook; Kim, Kyoung Doek; Herr, Y. H.

2003-01-01

Regulations and guidelines for radionuclide waste disposal require detailed information about the characteristics of radioactive waste drums prior to the transport to the disposal sites. Therefore, it is important to know the accurate radionuclide inventory of radioactive waste. However, estimation of radionuclide concentrations on drummed radioactive waste is difficult and unreliable. In order to overcome these difficulties, scaling factors have been used to assess the activities of radionuclides which could not be directly analyzed. A radionuclides assay system has been operated at Korean nuclear power plant (KORI site) since 1996 and consolidated scaling factor concept has played a dominant role in determination of radionuclides concentrations. For corrosion product radionuclides, generic scaling factors were used due to the similar trend and better-characterized properties of Korean analyzed data compared to the worldwide database. It is not easy to use the generic scaling factors for fission product and TRU radionuclides. Thus simple model reflecting the history of the operation of power plant and nuclear fuel condition is applied. However, some problems are still remained. For examples, disparity between the actual and ideal correlation pairs, inaccuracy of analyzed sample values, uncertainty in representative of derived scaling factor values and so on. As a result, the correlation ratios are somewhat dispersive. So it is planned to establish an assay system using more improved scaling factors. In this study, the scope of research is expanded and planned such as following. 1) Considering more assay target nuclides, 2) Considering more target NPPs, 3) More reliable sampling and measurement techniques, 4) Improvement of accuracy and representativeness of derived scaling factor values and 5) Conformation of correlation pairs based on Korean analyzed data. As this study progresses, it is possible to get more accurate and reliable prediction for the information of

Predisposal management of low and intermediate level radioactive waste. Safety guide

International Nuclear Information System (INIS)

2003-01-01

Radioactive waste is generated in the generation of electricity in nuclear power reactors and in the use of radioactive material in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized. The principles and requirements that govern the safety of the management of radioactive waste are presented in 'The Principles of Radioactive Waste Management', 'Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety' and 'Predisposal Management of Radioactive Waste, Including Decommissioning'. The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the principles and requirements established in Refs for the predisposal management of LLW. This Safety Guide deals with the safety issues associated with the predisposal management of LLW from nuclear fuel cycle facilities, large research and development installations and radioisotope production facilities. This includes all steps and activities in the management of waste, from its initial generation to its final acceptance at a waste disposal facility or the removal of regulatory control. The predisposal management of radioactive waste includes decommissioning. The term 'decommissioning' encompasses both the process of decommissioning a facility and the management of the waste that results (prior to its disposal). Recommendations on the process of decommissioning are provided in Refs. Recommendations on the management of the waste resulting from decommissioning are included in this Safety Guide. Although the mining and milling of uranium and thorium ores is part of the nuclear fuel cycle, the management of the operational waste (e.g. waste rock, tailings and effluent treatment waste) from these activities is not within the scope of this Safety Guide. The LLW that is

The study on safety facility criteria for radioactive waste repository

International Nuclear Information System (INIS)

Lee, S. H.; Choi, M. H.; Han, S. H. and others

1992-12-01

The radioactive waste repository are necessary to install the engineered safety systems to secure the safety for operation of the repository in the event of fire and earthquake. Since the development of safety facility criteria requires a thorough understanding about the characteristics of the engineered safety systems, we should investigate by means of literature survey and visit SKB. In particular, definition, composition of the systems, functional requirement of the systems, engineered safety systems of foreign countries, system design, operation and maintenance requirement should be investigated : fire protection system, ventilation system, drainage system, I and C system, electric system, radiation monitoring system. This proposed criteria consist of purpose, scope of application, ventilation system, fire protection system, drainage system, electric system and this proposed criteria can be applied as a basic reference for the final criteria

Household hazardous waste management: a review.

Science.gov (United States)

Inglezakis, Vassilis J; Moustakas, Konstantinos

2015-03-01

This paper deals with the waste stream of household hazardous waste (HHW) presenting existing management systems, legislation overview and other relevant quantitative and qualitative information. European Union legislation and international management schemes are summarized and presented in a concise manner by the use of diagrams in order to provide crucial information on HHW. Furthermore, sources and types, numerical figures about generation, collection and relevant management costs are within the scope of the present paper. The review shows that the term used to refer to hazardous waste generated in households is not clearly defined in legislation, while there is absence of specific acts regulating the management of HHW. The lack of obligation to segregate HHW from the household waste and the different terminology used makes it difficult to determine the quantities and composition of this waste stream, while its generation amount is relatively small and, therefore, is commonly overlooked in waste statistics. The paper aims to cover the gap in the related literature on a subject that is included within the crucial waste management challenges at world level, considering that HHW can also have impact on other waste streams by altering the redox conditions or causing direct reactions with other non hazardous waste substances. Copyright © 2014 Elsevier Ltd. All rights reserved.

Maintenance study for W-340 Waste Retrieval System

International Nuclear Information System (INIS)

Christensen, C.; Conner, C.C.; Sekot, J.P.

1994-05-01

This study was performed to identify attributes and maintainability requirements for the Tank Waste Retrieval System (TWRS). The system will be developed for Westinghouse Hanford Company in Richland, Washington, as an integrated system to perform waste removal in Tank C-106 and, thus, demonstrate technologies for tank remediation that will satisfy requirements of the Tri-Party Agreement. The study examines attributes of the TWRS, scope of maintenance operations required for the TWRS, maintenance requirements, and potential methods of performing maintenance functions. Recommendations are provided for consideration in the development of both the conceptual design and performance specification, which will be used in procuring the W-340 Waste Retrieval System

More reliable financing of future nuclear waste costs

International Nuclear Information System (INIS)

1994-01-01

This appendix contains seven reports written by consultants to the Commission. The report titles are: Basic document regarding the inquiry on fund management; Scenarios for growth and real interest rates in a long perspective; Stability of the Swedish financing system; Report concerning the financing of nuclear waste management in Sweden and Finland and the cost control system in Sweden; Evaluation of the cost estimates and calculation methods of SKB; A study of the costs for nuclear waste - The basis for cost estimation; A review of scope and costs for the Swedish system for management of nuclear waste. The four last reports are separately indexed

Radioactive waste management in the former USSR

Energy Technology Data Exchange (ETDEWEB)

Bradley, D.J.

1992-06-01

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

Radioactive waste management in the former USSR

International Nuclear Information System (INIS)

Bradley, D.J.

1992-06-01

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes

Time evolution of the general characteristics and Cu retention capacity in an acid soil amended with a bentonite winery waste.

Science.gov (United States)

Fernández-Calviño, David; Rodríguez-Salgado, Isabel; Pérez-Rodríguez, Paula; Nóvoa-Muñoz, Juan Carlos; Arias-Estévez, Manuel

2015-03-01

The effect of bentonite waste added to a "poor" soil on its general characteristic and copper adsorption capacity was assessed. The soil was amended with different bentonite waste concentrations (0, 10, 20, 40 and 80 Mg ha(-1)) in laboratory pots, and different times of incubation of samples were tested (one day and one, four and eight months). The addition of bentonite waste increased the pH, organic matter content and phosphorus and potassium concentrations in the soil, being stable for P and K, whereas the organic matter decreased with time. Additionally, the copper sorption capacity of the soil and the energy of the Cu bonds increased with bentonite waste additions. However, the use of this type of waste in soil presented important drawbacks for waste dosages higher than 20 Mg ha(-1), such as an excessive increase of the soil pH and an increase of copper in the soil solution. Copyright © 2014 Elsevier Ltd. All rights reserved.

Greater-confinement disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Trevorrow, L.E.; Gilbert, T.L.; Luner, C.; Merry-Libby, P.A.; Meshkov, N.K.; Yu, C.

1985-01-01

Low-level radioactive wastes include a broad spectrum of wastes that have different radionuclide concentrations, half-lives, and physical and chemical properties. Standard shallow-land burial practice can provide adequate protection of public health and safety for most low-level wastes, but a small volume fraction (about 1%) containing most of the activity inventory (approx.90%) requires specific measures known as ''greater-confinement disposal'' (GCD). Different site characteristics and different waste characteristics - such as high radionuclide concentrations, long radionuclide half-lives, high radionuclide mobility, and physical or chemical characteristics that present exceptional hazards - lead to different GCD facility design requirements. Facility design alternatives considered for GCD include the augered shaft, deep trench, engineered structure, hydrofracture, improved waste form, and high-integrity container. Selection of an appropriate design must also consider the interplay between basic risk limits for protection of public health and safety, performance characteristics and objectives, costs, waste-acceptance criteria, waste characteristics, and site characteristics. This paper presents an overview of the factors that must be considered in planning the application of methods proposed for providing greater confinement of low-level wastes. 27 refs

Geochemical Interactions in failed Co-Disposal Waste Packages for N Reactor and Ft. St. Vrain Spent Fuel and the Melt and Dilute Waste Form

International Nuclear Information System (INIS)

Arthur, S.E.; McNeish, J.

2002-01-01

The objective of this scientific analysis is to calculate the long-term geochemical behavior in a failed co-disposal waste package (WP) containing U. S. Department of Energy (DOE) spent nuclear fuel (SNF) and high level waste (HLW) glass. This analysis was prepared according to a Technical Work Plan (BSC 2002). Specifically the scope of these calculations is to determine: (1) The geochemical characteristics of the fluids inside the WP after breach, including the corrosion/dissolution of the initial WP configuration; (2) The transport of radionuclides of concern to performance assessment out of the degraded WP by infiltrating water; and (3) The range of parameter variation for additional laboratory and numerical evaluations. This analysis is limited to three SNF groups, uranium (U)/thorium (Th) carbide SNF (Group 5), U metal SNF (Group 7), and aluminum(Al)-based fuels (Group 9). Group 5 is represented by Ft. St. Vrain (FSV) U/Th carbide SNF, Group 7 is represented by N-Reactor U metal SNF, and Group 9 is represented by the Melt and Dilute (MandD) waste form developed from Al-based SNF. The DOE (2001a, Appendix A) describes all of these fuels. Table 1 shows the groups of DOE SNF, the representative SNF for each group, and the metric tons of heavy metal (MTHM) of SNF in each group

Igneous Intrusion Impacts on Waste Packages and Waste Forms

International Nuclear Information System (INIS)

P. Bernot

2004-01-01

The purpose of this model report is to assess the potential impacts of igneous intrusion on waste packages and waste forms in the emplacement drifts at the Yucca Mountain Repository. The model is based on conceptual models and includes an assessment of deleterious dynamic, thermal, hydrologic, and chemical impacts. This constitutes the waste package and waste form impacts submodel of the Total System Performance Assessment for the License Application (TSPA-LA) model assessing the impacts of a hypothetical igneous intrusion event on the repository total system performance. This submodel is carried out in accordance with Technical Work Plan for Waste Form Degradation Modeling, Testing, and Analyses in Support of SR and LA (BSC 2003a) and Total System Performance Assessment-License Application Methods and Approaches (BSC 2002a). The technical work plan is governed by the procedures of AP-SIII.10Q, Models. Any deviations from the technical work plan are documented in the TSPA-LA approach to implementing the models for waste package and waste form response during igneous intrusion is based on identification of damage zones. Zone 1 includes all emplacement drifts intruded by the basalt dike, and Zone 2 includes all other emplacement drifts in the repository that are not in Zone 1. This model report will document the following model: (1) Impacts of magma intrusion on the components of engineered barrier system (e.g., drip shields and cladding) of emplacement drifts in Zone 1, and the fate of waste forms. (2) Impacts of conducting magma heat and diffusing magma gases on the drip shields, waste packages, and cladding in the Zone 2 emplacement drifts adjacent to the intruded drifts. (3) Impacts of intrusion on Zone 1 in-drift thermal and geochemical environments, including seepage hydrochemistry. The scope of this model only includes impacts to the components stated above, and does not include impacts to other engineered barrier system (EBS) components such as the invert and

Igneous Intrusion Impacts on Waste Packages and Waste Forms

Energy Technology Data Exchange (ETDEWEB)

P. Bernot

2004-08-16

The purpose of this model report is to assess the potential impacts of igneous intrusion on waste packages and waste forms in the emplacement drifts at the Yucca Mountain Repository. The model is based on conceptual models and includes an assessment of deleterious dynamic, thermal, hydrologic, and chemical impacts. This constitutes the waste package and waste form impacts submodel of the Total System Performance Assessment for the License Application (TSPA-LA) model assessing the impacts of a hypothetical igneous intrusion event on the repository total system performance. This submodel is carried out in accordance with Technical Work Plan for Waste Form Degradation Modeling, Testing, and Analyses in Support of SR and LA (BSC 2003a) and Total System Performance Assessment-License Application Methods and Approaches (BSC 2002a). The technical work plan is governed by the procedures of AP-SIII.10Q, Models. Any deviations from the technical work plan are documented in the TSPA-LA approach to implementing the models for waste package and waste form response during igneous intrusion is based on identification of damage zones. Zone 1 includes all emplacement drifts intruded by the basalt dike, and Zone 2 includes all other emplacement drifts in the repository that are not in Zone 1. This model report will document the following model: (1) Impacts of magma intrusion on the components of engineered barrier system (e.g., drip shields and cladding) of emplacement drifts in Zone 1, and the fate of waste forms. (2) Impacts of conducting magma heat and diffusing magma gases on the drip shields, waste packages, and cladding in the Zone 2 emplacement drifts adjacent to the intruded drifts. (3) Impacts of intrusion on Zone 1 in-drift thermal and geochemical environments, including seepage hydrochemistry. The scope of this model only includes impacts to the components stated above, and does not include impacts to other engineered barrier system (EBS) components such as the invert and

Waste predisposal management

International Nuclear Information System (INIS)

2005-01-01

All Member States have to a large or small extent nuclear activities that generate radioactive wastes. Hospitals, research in biomedicine or in agriculture, and some industrial applications, beside other large nuclear activities such as Nuclear Power Plants and Nuclear Research, generate unconditioned liquid or solid radioactive wastes that have to be treated, conditioned and stored prior final disposal. Countries with small nuclear activities require of organizations and infrastructure as to be able to manage, in a safe manner, the wastes that they generate. Predisposal management of radioactive waste is any step carried out to convert raw waste into a stable form suitable for the safe disposal, such as pre-treatment, treatment, storage and relevant transport. Transport of radioactive waste do not differ, in general, from other radioactive material and so are not considered within the scope of this fact sheet (Nevertheless the Agency, within the Nuclear Safety Department, has created a special Unit that might give advise Member States in this area). Predisposal management is comprised of a set of activities whose implementation may take some time. In most of the cases, safety issues and strategic and economical considerations have to be solved prior the main decisions are taken. The International Atomic Energy Agency provides assistance for the management of radioactive waste at national and operating level, in the definition and/or implementation of the projects. The services could include, but are not limited to guidance in the definition of national waste management strategy and its implementation, definition of the most adequate equipment and practices taking into account specific Member State conditions, as well as assisting in the procurement, technical expertise for the evaluation of current status of operating facilities and practical guidance for the implementation of corrective actions, assistance in the definition of waste acceptance criteria for

Avoidable waste management costs

International Nuclear Information System (INIS)

Hsu, K.; Burns, M.; Priebe, S.; Robinson, P.

1995-01-01

This report describes the activity based costing method used to acquire variable (volume dependent or avoidable) waste management cost data for routine operations at Department of Energy (DOE) facilities. Waste volumes from environmental restoration, facility stabilization activities, and legacy waste were specifically excluded from this effort. A core team consisting of Idaho National Engineering Laboratory, Los Alamos National Laboratory, Rocky Flats Environmental Technology Site, and Oak Ridge Reservation developed and piloted the methodology, which can be used to determine avoidable waste management costs. The method developed to gather information was based on activity based costing, which is a common industrial engineering technique. Sites submitted separate flow diagrams that showed the progression of work from activity to activity for each waste type or treatability group. Each activity on a flow diagram was described in a narrative, which detailed the scope of the activity. Labor and material costs based on a unit quantity of waste being processed were then summed to generate a total cost for that flow diagram. Cross-complex values were calculated by determining a weighted average for each waste type or treatability group based on the volume generated. This study will provide DOE and contractors with a better understanding of waste management processes and their associated costs. Other potential benefits include providing cost data for sites to perform consistent cost/benefit analysis of waste minimization and pollution prevention (WMIN/PP) options identified during pollution prevention opportunity assessments and providing a means for prioritizing and allocating limited resources for WMIN/PP

Avoidable waste management costs

Energy Technology Data Exchange (ETDEWEB)

Hsu, K.; Burns, M.; Priebe, S.; Robinson, P.

1995-01-01

This report describes the activity based costing method used to acquire variable (volume dependent or avoidable) waste management cost data for routine operations at Department of Energy (DOE) facilities. Waste volumes from environmental restoration, facility stabilization activities, and legacy waste were specifically excluded from this effort. A core team consisting of Idaho National Engineering Laboratory, Los Alamos National Laboratory, Rocky Flats Environmental Technology Site, and Oak Ridge Reservation developed and piloted the methodology, which can be used to determine avoidable waste management costs. The method developed to gather information was based on activity based costing, which is a common industrial engineering technique. Sites submitted separate flow diagrams that showed the progression of work from activity to activity for each waste type or treatability group. Each activity on a flow diagram was described in a narrative, which detailed the scope of the activity. Labor and material costs based on a unit quantity of waste being processed were then summed to generate a total cost for that flow diagram. Cross-complex values were calculated by determining a weighted average for each waste type or treatability group based on the volume generated. This study will provide DOE and contractors with a better understanding of waste management processes and their associated costs. Other potential benefits include providing cost data for sites to perform consistent cost/benefit analysis of waste minimization and pollution prevention (WMIN/PP) options identified during pollution prevention opportunity assessments and providing a means for prioritizing and allocating limited resources for WMIN/PP.

Radionuclide Inventories for DOE SNF Waste Stream and Uranium/Thorium Carbide Fuels

International Nuclear Information System (INIS)

K.L. Goluoglu

2000-01-01

The objective of this calculation is to generate radionuclide inventories for the Department of Energy (DOE) spent nuclear fuel (SNF) waste stream destined for disposal at the potential repository at Yucca Mountain. The scope of this calculation is limited to the calculation of two radionuclide inventories; one for all uranium/thorium carbide fuels in the waste stream and one for the entire waste stream. These inventories will provide input in future screening calculations to be performed by Performance Assessment to determine important radionuclides

2014 Zero Waste Strategic Plan Executive Summary.

Energy Technology Data Exchange (ETDEWEB)

Wrons, Ralph J.

2016-05-01

Sandia National Laboratories/New Mexico is located in Albuquerque, New Mexico, primarily on Department of Energy (DOE) permitted land on approximately 2,800 acres of Kirtland Air Force Base. There are approximately 5.5 million square feet of buildings, with a workforce of approximately 9200 personnel. Sandia National Laboratories Materials Sustainability and Pollution Prevention (MSP2) program adopted in 2008 an internal team goal for New Mexico site operations for Zero Waste to Landfill by 2025. Sandia solicited a consultant to assist in the development of a Zero Waste Strategic Plan. The Zero Waste Consultant Team selected is a partnership of SBM Management Services and Gary Liss & Associates. The scope of this Plan is non-hazardous solid waste and covers the life cycle of material purchases to the use and final disposal of the items at the end of their life cycle.

The effect of vibration on alpha radiolysis of transuranic (TRU) waste

International Nuclear Information System (INIS)

Zerwekh, A.; Kosiewicz, S.; Warren, J.

1993-01-01

This paper reports on previously unpublished scoping work related to the potential for vibration to redistribute radionuclides on transuranic (TRU) waste. If this were to happen, the amount of gases generated, including hydrogen, could be increased above the undisturbed levels. This could be an important consideration for transport of TRU wastes either at DOE sites or from them to a future repository, e.g., the Waste Isolation Pilot Plant (WIPP). These preliminary data on drums of real waste seem to suggest that radionuclide redistribution does not occur. However improvements in the experimental methodology are suggested to enhance safety of future experiments on real wastes as well as to provide more rigorous data

Modification of the ventilation system at Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Sethi, S.C.

1987-01-01

The WIPP (Waste Isolation Pilot Plant) Project near Carlsbad, New Mexico, is a research and development project sponsored by the US Department of Energy, designed to demonstrate the safe disposal of radioactive waste. A mine (repository) is being developed 2,150 feet below the surface in a thick salt bed, which will serve as the disposal medium. The underground ventilation system for the WIPP project was originally designed based on a fixed project scope. The design criteria and ventilation requirements were developed for the performance of various activities as then envisioned towards the achievement of this goal. However, in light of new information and actual site-specific experience at WIPP leading to a clearer definition of the scope-related programs and activities, it was realized that the existing ventilation system may need to be modified

Characteristics of metal waste forms containing technetium and uranium

Energy Technology Data Exchange (ETDEWEB)

Fortner, J.A.; Kropf, A.J.; Ebert, W.L. [Argonne National Laboratory, Argonne, IL 60439 (United States)

2013-07-01

2 prototype alloys: RAW-1(Tc) and RAW-2(UTc) suitable for a wide range of waste stream compositions are being evaluated to support development of a waste form degradation model that can be used to calculate radionuclide source terms for a range of waste form compositions and disposal environments. Tests and analyses to support formulation of waste forms and development of the degradation model include detailed characterizations of the constituent phases using SEM/EDS and TEM, electrochemical tests to quantify the oxidation behavior and kinetics of the individual and coupled phases under a wide range of environmental conditions, and corrosion tests to measure the gross release kinetics of radionuclides under aggressive test conditions.

Product consistency test and toxicity characteristic leaching procedure results of the ceramic waste form from the electrometallurgical treatment process for spent fuel

International Nuclear Information System (INIS)

Johnson, S. G.; Adamic, M. L.: DiSanto, T.; Warren, A. R.; Cummings, D. G.; Foulkrod, L.; Goff, K. M.

1999-01-01

The ceramic waste form produced from the electrometallurgical treatment of sodium bonded spent fuel from the Experimental Breeder Reactor-II was tested using two immersion tests with separate and distinct purposes. The product consistency test is used to assess the consistency of the waste forms produced and thus is an indicator of a well-controlled process. The toxicity characteristic leaching procedure is used to determine whether a substance is to be considered hazardous by the Environmental Protection Agency. The proposed high level waste repository will not be licensed to receive hazardous waste, thus any waste forms destined to be placed there cannot be of a hazardous nature as defined by the Resource Conservation and Recovery Act. Results are presented from the first four fully radioactive ceramic waste forms produced and from seven ceramic waste forms produced from cold surrogate materials. The fully radioactive waste forms are approximately 2 kg in weight and were produced with salt used to treat 100 driver subassemblies of spent fuel

Hanford Waste Vitrification Plant Technology Plan

International Nuclear Information System (INIS)

Sexton, R.A.

1988-06-01

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

DESIGN ANALYSIS FOR THE NAVAL SNF WASTE PACKAGE

International Nuclear Information System (INIS)

T.L. Mitchell

2000-01-01

The purpose of this analysis is to demonstrate the design of the naval spent nuclear fuel (SNF) waste package (WP) using the Waste Package Department's (WPD) design methodologies and processes described in the ''Waste Package Design Methodology Report'' (CRWMS MandO [Civilian Radioactive Waste Management System Management and Operating Contractor] 2000b). The calculations that support the design of the naval SNF WP will be discussed; however, only a sub-set of such analyses will be presented and shall be limited to those identified in the ''Waste Package Design Sensitivity Report'' (CRWMS MandO 2000c). The objective of this analysis is to describe the naval SNF WP design method and to show that the design of the naval SNF WP complies with the ''Naval Spent Nuclear Fuel Disposal Container System Description Document'' (CRWMS MandO 1999a) and Interface Control Document (ICD) criteria for Site Recommendation. Additional criteria for the design of the naval SNF WP have been outlined in Section 6.2 of the ''Waste Package Design Sensitivity Report'' (CRWMS MandO 2000c). The scope of this analysis is restricted to the design of the naval long WP containing one naval long SNF canister. This WP is representative of the WPs that will contain both naval short SNF and naval long SNF canisters. The following items are included in the scope of this analysis: (1) Providing a general description of the applicable design criteria; (2) Describing the design methodology to be used; (3) Presenting the design of the naval SNF waste package; and (4) Showing compliance with all applicable design criteria. The intended use of this analysis is to support Site Recommendation reports and assist in the development of WPD drawings. Activities described in this analysis were conducted in accordance with the technical product development plan (TPDP) ''Design Analysis for the Naval SNF Waste Package (CRWMS MandO 2000a)

The scope and nature of the problem of high level nuclear waste disposal

International Nuclear Information System (INIS)

Jennekens, J.

1981-09-01

The disposal of high level nuclear waste poses a challenge to the Canadian technical and scientific communities, but a much greater challenge to government and industry leaders who must convince the public that the so-called 'problem' can be resolved by a pragmatic approach utilizing existing skills and knowledge. This paper outlines the objectives of radioactive waste management, the quantities of high level waste expected to be produced by the Canadian nuclear power program, the regulatory process which will apply and the government initiatives which have been and will be taken to ensure that the health, safety, security, and environmental interests of the public will be protected. (author)

Nuclear waste management: the ocean alternative

International Nuclear Information System (INIS)

Jackson, T.C.

1981-01-01

Both the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency (NEA) are working on sea disposal. This forum related to this problem. Past practices and policies for sea disposal of radioactive wastes are examined in this paper by Robert S. Dyer, Office of Radiation Programs, US Environmental Protection Agency. Mr. Dyer's analysis served as the principal background paper for the Forum. He reviewed the scope of American sea disposal programs between 1946 and 1970; then he discussed the concentrations of radioactive wastes at 35 dump sites used by the United States. The US decision to halt sea disposal of low-level radioactive wastes in 1970 and current federal laws are also discussed. International regulations based on the London Dumping Convention and a review of sea disposal practices by other nations are included

Characteristics of medically related low-level radioactive waste

International Nuclear Information System (INIS)

Weir, G.J. Jr.; Teele, B.

1986-07-01

This report describes a survey that identified the current sources of medically generated radioactive wastes. Included are recommendations on how to reduce the volume of medically-related material classified as low-level radioactive wastes, to improve handling techniques for long-lived radioisotopes, and for options for the use of radioactive materials in medical studies. 8 refs., 11 tabs

Licence applications for low and intermediate level waste predisposal facilities: A manual for operators

International Nuclear Information System (INIS)

2009-07-01

This publication covers all predisposal waste management facilities and practices for receipt, pretreatment (sorting, segregation, characterization), treatment, conditioning, internal relocation and storage of low and intermediate level radioactive waste, including disused sealed radioactive sources. The publication contains an Annex presenting the example of a safety assessment for a small radioactive waste storage facility. Facilities dealing with both short lived and long lived low and intermediate level waste generated from nuclear applications and from operation of small nuclear research reactors are included in the scope. Processing and storage facilities for high activity disused sealed sources and sealed sources containing long lived radionuclides are also covered. The publication does not cover facilities processing or storing radioactive waste from nuclear power plants or any other industrial scale nuclear fuel cycle facilities. Disposal facilities are excluded from the scope of this publication. Authorization process can be implemented in several stages, which may start at the site planning and the feasibility study stage and will continue through preliminary design, final design, commissioning, operation and decommissioning stages. This publication covers primarily the authorization needed to take the facility into operation

Draft Waste Management Programmatic Environmental Impact Statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume 3, Appendix A: Public response to revised NOI, Appendix B: Environmental restoration, Appendix C, Environmental impact analysis methods, Appendix D, Risk

International Nuclear Information System (INIS)

1995-08-01

Volume three contains appendices for the following: Public comments do DOE's proposed revisions to the scope of the waste management programmatic environmental impact statement; Environmental restoration sensitivity analysis; Environmental impacts analysis methods; and Waste management facility human health risk estimates

Draft Waste Management Programmatic Environmental Impact Statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume 3, Appendix A: Public response to revised NOI, Appendix B: Environmental restoration, Appendix C, Environmental impact analysis methods, Appendix D, Risk

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-01

Volume three contains appendices for the following: Public comments do DOE`s proposed revisions to the scope of the waste management programmatic environmental impact statement; Environmental restoration sensitivity analysis; Environmental impacts analysis methods; and Waste management facility human health risk estimates.

Leachability characteristics of beryllium in redmud waste and its stabilization in cement

International Nuclear Information System (INIS)

Saradhi, I.V.; Mahadevan, T.N.; Krishnamoorthy, T.M.

1999-01-01

More than 70% of the beryl ore processed by the Beryllium Metal Plant at the BARC Vashi Complex ends up as redmud waste. The presence of significant quantities (0.4 to 0.8%) of beryllium in the redmud qualifies it as hazardous requiring safe handling, storage and disposal. The waste also contains 0.09% of water soluble fluoride. The various standard protocol of procedures were employed to estimate the leachability of beryllium from redmud for both short term and long term periods. Nearly 50% of beryllium present in redmud is leachable in water. We have tried the stabilization of redmud using portland cement. The proportion of redmud to cement was in the ratio of 1:1, 1:2 and 1:4. The blocks were cast, cured and used in the leachability experiments using standard protocols as above. The results of the TCLP test gave the levels of beryllium well below the standard limits in the TCLP extract of cement stabilized waste indicating the suitability of stabilization of redmud with cement whereas that of raw waste (redmud) are much higher than the prescribed limits. The total leach percent of beryllium in 1:2 block is 0.05% over period of 164 days whereas 1:1 and 1:4 gave a leach percent of 0.26 and 0.15% respectively. The DLT results indicate, diffusion controlled release of beryllium from the cement stabilized redmud blocks. The effective diffusion coefficient of beryllium obtained from the modelling study is 10 orders of magnitude less than the molecular diffusion coefficient of beryllium indicating the effectiveness of cement stabilization. From the detailed experiments performed, it is felt that 1:2 proportion of redmud and cement will be the best suited option for stabilization of redmud waste. The 1:1 proportion of redmud to cement mixture which could not be cast into compact cement blocks also exhibited very low leachability characteristics similar to 1:2 and 1:4 and can be be favourably considered for stabilization in case of space constraints at storage sites. The

State of the art report on bituminized waste forms of radioactive wastes

International Nuclear Information System (INIS)

Kim, Tae Kook; Shon, Jong Sik; Kim, Kil Jeong; Lee, Kang Moo; Jung, In Ha

1998-03-01

In this report, research and development results on the bituminization of radioactive wastes are closely reviewed, especially those regarding waste treatment technologies, waste solidifying procedures and the characteristics of asphalt and solidified forms. A new concept of the bituminization method is suggested in this report which can improve the characteristics of solidified forms. Stable solid forms with high leach resistance, high thermal resistance and good compression strength were produced by the suggested bituminization method, in which spent polyethylene from agricultural farms was added. This report can help further research and development of improved bituminized forms of radioactive wastes that will maintain long term stabilities in disposal sites. (author). 59 refs., 19 tabs., 18 figs

Radioactive waste in Federal Germany

International Nuclear Information System (INIS)

Brennecke, P.; Schumacher, J.; Warnecke, E.

1988-01-01

The Physikalisch-Technische Bundesanstalt (PTB) is responsible for the long-term storage and disposal of radioactive waste according to the Federal Atomic Energy Act. On behalf of the Federal Minister of the Environment, Nature Conservation and Nuclear Safety, since 1985, the PTB has been carrying out annual inquiries into the amounts of radioactive waste produced in the Federal Republic of Germany. Within the scope of this inquiry performed for the preceding year, the amounts of unconditioned and conditioned waste are compiled on a producer- and plant-specific basis. On the basis of the inquiry for 1986 and of data presented to the PTB by the waste producers, future amounts of radioactive waste have been estimated up to the year 2000. The result of this forecast is presented. In the Federal Republic of Germany two sites are under consideration for disposal of radioactive waste. In the abandoned Konrad iron mine in Salzgitter-Bleckenstedt it is intended to dispose of such radioactive waste which has a negligible thermal influence upon the host rock. The Gorleben salt dome is being investigated for its suitability for the disposal of all kinds of solid and solidified radioactive wastes, especially of heat-generating waste. Comparing the estimated amount of radioactive wastes with the capacity of both repositories it may be concluded that the Konrad and Gorleben repositories will provide sufficient capacity to ensure the disposal of all kinds of radioactive waste on a long-term basis in the Federal Republic of Germany. 1 fig., 2 tabs

COMPAS: a European project on the ''comparison of alternative waste management strategies for long-lived radioactive wastes''. Scope, working methods and conclusions

International Nuclear Information System (INIS)

Dutton, L.M.C.; Hillis, Z.K.; Roehlig, K.J.

2004-01-01

The paper presents the content and major findings of a project on the ''COMParison of Alternative waste management Strategies for long-lived radioactive wastes'' (COMPAS) carried out within the 5 th framework programme of the European commission. Under the leadership of NNC (UK), the project was carried out by individuals representing waste management organisations from 15 European countries. After having compiled information on the nature and amount of long-lived radioactive waste to be managed, issues influencing the selection of waste management strategies and options, presently adopted national strategies as well as options for the future were addressed. Conclusions concerning key issues for the success or otherwise of strategies and management solutions were drawn. (orig.)

Thermal Response of the 21-PWR Waste Package to a Fire Accident

International Nuclear Information System (INIS)

F.P. Faucher; H. Marr; M.J. Anderson

2000-01-01

The objective of this calculation is to evaluate the thermal response of the 21-PWR WP (pressurized water reactor waste package) to the regulatory fire event. The scope of this calculation is limited to the two-dimensional waste package temperature calculations to support the waste package design. The information provided by the sketches attached to this calculation (Attachment IV) is that of the potential design of the type of waste package considered in this calculation. The procedure AP-3.12Q.Calculations (Reference 1), and the Development Plan (Reference 24) are used to develop this calculation

Report on the evaluation under the Act No 24/2006 of Coll. Environmental Impact Assessment Law Extension of National Radioactive Waste Repository in Mochovce for disposal low-level radioactive waste and construction of very low-level radioactive waste repository

International Nuclear Information System (INIS)

Hanusik, V.; Moravek, J.; Kusovska, Z.

2011-01-01

The report elaborated assessment of the environmental impact of extension of the National Radioactive Waste Repository in Mochovce for disposal of low and intermediate level radioactive wastes. Within this repository also the premises for very low level radioactive waste deposition should be built. The assessment report was prepared according to the Act no. 24/2006 Coll, as amended 'On the assessment of environmental impacts' Annex No. 11 upon The scope of assessment issued by the competent authority on the basis of assessment of Intent for this action. The report was prepared in VUJE, Inc. Trnava for Nuclear and Decommissioning Company, Inc. Bratislava (JAVYS).

300 Area waste acid treatment system closure plan

International Nuclear Information System (INIS)

LUKE, S.N.

1999-01-01

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOERL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion includes closure plan documentation submitted for individual, treatment, storage, and/or disposal units undergoing closure, such as the 300 Area Waste Acid Treatment System. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Whenever appropriate, 300 Area Waste Acid Treatment System documentation makes cross-reference to the General Information Portion, rather than duplicating text. This 300 Area Waste Acid Treatment System Closure Plan (Revision 2) includes a Hanford Facility Dangerous Waste Permit Application, Part A, Form 3. Information provided in this closure plan is current as of April 1999

300 Area waste acid treatment system closure plan

Energy Technology Data Exchange (ETDEWEB)

LUKE, S.N.

1999-05-17

The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOERL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion includes closure plan documentation submitted for individual, treatment, storage, and/or disposal units undergoing closure, such as the 300 Area Waste Acid Treatment System. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Whenever appropriate, 300 Area Waste Acid Treatment System documentation makes cross-reference to the General Information Portion, rather than duplicating text. This 300 Area Waste Acid Treatment System Closure Plan (Revision 2) includes a Hanford Facility Dangerous Waste Permit Application, Part A, Form 3. Information provided in this closure plan is current as of April 1999.

Indirect Determination of Chemical Composition and Fuel Characteristics of Solid Waste

DEFF Research Database (Denmark)

Riber, Christian; Christensen, Thomas Højlund

Determination of chemical composition of solid waste can be performed directly or indirectly by analysis of combustion products. The indirect methodology instrumented by a full scale incinerator is the only method that can conclude on elements in trace concentrations. These elements are of great...... interest in evaluating waste management options by for example LCA modeling. A methodology description of indirect determination of chemical composition and fuel properties of waste is provided and validated by examples. Indirect analysis of different waste types shows that the chemical composition...... is significantly dependent on waste type. And the analysis concludes that the transfer of substances in the incinerator is a function of waste chemical content, incinerator technology and waste physical properties. The importance of correct representation of rare items in the waste with high concentrations...

Scope Definition

DEFF Research Database (Denmark)

Bjørn, Anders; Owsianiak, Mikołaj; Laurent, Alexis

2018-01-01

The scope definition is the second phase of an LCA. It determines what product systems are to be assessed and how this assessment should take place. This chapter teaches how to perform a scope definition. First, important terminology and key concepts of LCA are introduced. Then, the nine items...... making up a scope definition are elaborately explained: (1) Deliverables. (2) Object of assessment, (3) LCI modelling framework and handling of multifunctional processes, (4) System boundaries and completeness requirements, (5) Representativeness of LCI data, (6) Preparing the basis for the impact...... assessment, (7) Special requirements for system comparisons, (8) Critical review needs and (9) Planning reporting of results. The instructions relate both to the performance and reporting of a scope definition and are largely based on ILCD....

Review of the factors affecting the selection and implementation of waste management technologies

International Nuclear Information System (INIS)

1999-08-01

The objective of this publication is to identify and critically review the factors affecting the selection of waste management strategies and technologies; summarize and discuss the options available, and offer a systematic approach for considering these factors to design, install and operate appropriate technologies for waste streams generated. The scope of this publication includes the management of radioactive waste from all orientations including low and intermediate level waste arising from the production of radionuclides and their application in industry, agriculture, medicine, education and research; waste generated from research reactors, power reactors and from nuclear fuel cycle activities including reprocessing high level waste. Although waste from decommissioning is not specifically addressed, the management of this waste is not significantly different from other types of waste in the same category

Review of the factors affecting the selection and implementation of waste management technologies

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-08-01

The objective of this publication is to identify and critically review the factors affecting the selection of waste management strategies and technologies; summarize and discuss the options available, and offer a systematic approach for considering these factors to design, install and operate appropriate technologies for waste streams generated. The scope of this publication includes the management of radioactive waste from all orientations including low and intermediate level waste arising from the production of radionuclides and their application in industry, agriculture, medicine, education and research; waste generated from research reactors, power reactors and from nuclear fuel cycle activities including reprocessing high level waste. Although waste from decommissioning is not specifically addressed, the management of this waste is not significantly different from other types of waste in the same category 32 refs, 11 figs, 12 tabs

Environmental Restoration Progam Waste Minimization and Pollution Prevention Awareness Program Plan

Energy Technology Data Exchange (ETDEWEB)

Grumski, J. T.; Swindle, D. W.; Bates, L. D.; DeLozier, M. F.P.; Frye, C. E.; Mitchell, M. E.

1991-09-30

In response to DOE Order 5400.1 this plan outlines the requirements for a Waste Minimization and Pollution Prevention Awareness Program for the Environmental Restoration (ER) Program at Martin Marietta Energy System, Inc. Statements of the national, Department of Energy, Energy Systems, and Energy Systems ER Program policies on waste minimization are included and reflect the attitudes of these organizations and their commitment to the waste minimization effort. Organizational responsibilities for the waste minimization effort are clearly defined and discussed, and the program objectives and goals are set forth. Waste assessment is addressed as being a key element in developing the waste generation baseline. There are discussions on the scope of ER-specific waste minimization techniques and approaches to employee awareness and training. There is also a discussion on the process for continual evaluation of the Waste Minimization Program. Appendixes present an implementation schedule for the Waste Minimization and Pollution Prevention Program, the program budget, an organization chart, and the ER waste minimization policy.

Environmental Restoration Progam Waste Minimization and Pollution Prevention Awareness Program Plan

International Nuclear Information System (INIS)

1991-01-01

In response to DOE Order 5400.1 this plan outlines the requirements for a Waste Minimization and Pollution Prevention Awareness Program for the Environmental Restoration (ER) Program at Martin Marietta Energy System, Inc. Statements of the national, Department of Energy, Energy Systems, and Energy Systems ER Program policies on waste minimization are included and reflect the attitudes of these organizations and their commitment to the waste minimization effort. Organizational responsibilities for the waste minimization effort are clearly defined and discussed, and the program objectives and goals are set forth. Waste assessment is addressed as being a key element in developing the waste generation baseline. There are discussions on the scope of ER-specific waste minimization techniques and approaches to employee awareness and training. There is also a discussion on the process for continual evaluation of the Waste Minimization Program. Appendixes present an implementation schedule for the Waste Minimization and Pollution Prevention Program, the program budget, an organization chart, and the ER waste minimization policy

2009 National inventory of radioactive material and wastes. Descriptive catalogue of waste types

International Nuclear Information System (INIS)

2009-01-01

The various types of radioactive wastes (produced or to be produced in France) are presented. Each radioactive waste family (i.e. having analogous characteristics) is described, with a thorough information on their general characteristics, their localization in France, the waste management process, and details on their origin and owner, state of production, volume and conditioning, etc. Data are given concerning produced quantities and radioactivity levels at the end of 2007 (with forecasts for 2020 and 2030), mean package radioactivity, presence of possibly toxic chemicals, etc

Developing Capacities in Radioactive Waste Management

International Nuclear Information System (INIS)

Yusuf, Omar

2014-01-01

As the Agency’s main service-delivery mechanism, the IAEA’s technical cooperation (TC) programme plays a large part in supporting radioactive waste management around the world, helping to share information on the topic, and training personnel in the proper treatment and disposal of radioactive waste. The TC programme supports the development of policies and strategies, the assessment and upgrading (if necessary) of existing facilities, and the implementation of new management facilities, especially for near surface disposal. The programme also helps to develop competence in geological disposal for Member States operating nuclear power plants. This article presents just a few project examples to illustrate the scope of the programme

Domestic Waste Management In Samarinda City

Directory of Open Access Journals (Sweden)

Florentinus Sudiran

2017-11-01

Full Text Available Garbage is solid wastes which have mostly organic composition and the rest consists of plastic paper cloth rubber bone and others. Garbage disposal in urban areas is often a burden because it involves financing for waste transport disposal sites health and environmental hygiene. The burden of waste management is increasing as the volume of waste increases due to population growth and community behavior. Samarinda as a developing city also experienced the problem. Problems encountered include low service coverage especially for domestic waste high landfill demand and high government subsidies that resulted in the community no matter the amount of waste generated. The purpose of this study is to determine whether the waste management by the government of Samarinda City from management management aspects institutional capacity and financing system is environmentally sound. The method used is non experimental method and do direct observation in the field. Data collection with questionnaires field observations document analysis and literature. Based on the results of the study concluded as follows Waste management by the Government of Samarinda City as a whole has been good and has environmentally minded by running the system of collecting transporting and destruction and separating waste from waste processing and sources into compost fertilizer though still very limited in scope. Waste management by the capital intensive Samarinda City Government leads to high costs by the operational costs of trucks and other vehicles.

Methods and Production of Cementation Materials for Immobilisation into Waste Form. Research of Cementation Processes for Specific Liquid Radioactive Waste Streams of Radiochemical Plants

International Nuclear Information System (INIS)

Sukhanov, L.P.

2013-01-01

In the near future Russian Federation is planning to use industrial cementation facilities at two radiochemical combines - PA 'Mayak' and Mountain Chemical Combine. Scope of the research within the IAEA CRP contact No. 14176 included the development of cementation processes for specfic liquid radioactive waste streams that are present in these enterprisers. The research on cementation of liquid waste from spent nuclear fuel reprocessing at PA 'Mayak' allowed obtaining experimental data characterizing the technological process and basic characteristics of the produced cement compounds (e.g. mechanical strength, water resistance, frost resistance, flowability, etc.) immobilizing different streams of waste (e.g. hydrated-salt sludges, filter material pulps, mixture of hydrated salt slurries and filter material pulps, tritium liquid waste). Determined optimum technological parameters will allow industrial scale production of cement compound with required quality and higher flowability that is necessary for providing uniform filling of compartments of storage facilities at these sites. The research has been also carried out for the development of cementation technology for immobilization of pulps from storage tanks of Mountain Chemical Combine radiochemical plant. Cementation of such pulps is a difficult technological task because pulps are of complex chemical composition (e.g. hydroxides of manganese, iron, nickel, etc., as well as silicon oxide) and a relatively high activity. The research of cementation process selection for these pulps included studies of the impact of sorbing additive type and content on cement compounds leachability, flowability, impact of cement compound age to its mechanical strength, heat generation of cement compounds and others. The research results obtained allowed testing of cementation facility with a pulse type mixer on the full-scale. Use of such mixer for pulp cementation makes possible to prepare a homogeneous cement compound with the

Treatment of liquid wastes from uranium hydrometallurgy

International Nuclear Information System (INIS)

Moraga G, J.C.

1988-01-01

Different treatments for low activity liquid wastes, generated by the hidromettalurgy of uranium ore are studied. A process of treatment was chosen which includes a neutralization with lime and limestone and a selective removal of Ra-226, through ion-exchange resins. A plant, with a capacity of treatment of 1 m 3 /h of liquid effluents was scoped. (author)

CSNF WASTE FORM DEGRADATION: SUMMARY ABSTRACTION

Energy Technology Data Exchange (ETDEWEB)

J.C. CUNNANE

2004-08-31

The purpose of this model report is to describe the development and validation of models that can be used to calculate the release of radionuclides from commercial spent nuclear fuel (CSNF) following a hypothetical breach of the waste package and fuel cladding in the repository. The purpose also includes describing the uncertainties associated with modeling the radionuclide release for the range of CSNF types, exposure conditions, and durations for which the radionuclide release models are to be applied. This document was developed in accordance with Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package (BSC 2004 [DIRS 169944]). This document considers radionuclides to be released from CSNF when they are available for mobilization by gas-phase mass transport, or by dissolution or colloid formation in water that may contact the fuel. Because other reports address limitations on the dissolved and colloidal radionuclide concentrations (BSC 2004 [DIRS 169944], Table 2-1), this report does not address processes that control the extent to which the radionuclides released from CSNF are mobilized and transported away from the fuel either in the gas phase or in the aqueous phase as dissolved and colloidal species. The scope is limited to consideration of degradation of the CSNF rods following an initial breach of the cladding. It considers features of CSNF that limit the availability of individual radionuclides for release into the gaseous or aqueous phases that may contact the fuel and the processes and events expected to degrade these CSNF features. In short, the purpose is to describe the characteristics of breached fuel rods and the degradation processes expected to influence radionuclide release.

CSNF WASTE FORM DEGRADATION: SUMMARY ABSTRACTION

International Nuclear Information System (INIS)

CUNNANE, J.C.

2004-01-01

The purpose of this model report is to describe the development and validation of models that can be used to calculate the release of radionuclides from commercial spent nuclear fuel (CSNF) following a hypothetical breach of the waste package and fuel cladding in the repository. The purpose also includes describing the uncertainties associated with modeling the radionuclide release for the range of CSNF types, exposure conditions, and durations for which the radionuclide release models are to be applied. This document was developed in accordance with Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package (BSC 2004 [DIRS 169944]). This document considers radionuclides to be released from CSNF when they are available for mobilization by gas-phase mass transport, or by dissolution or colloid formation in water that may contact the fuel. Because other reports address limitations on the dissolved and colloidal radionuclide concentrations (BSC 2004 [DIRS 169944], Table 2-1), this report does not address processes that control the extent to which the radionuclides released from CSNF are mobilized and transported away from the fuel either in the gas phase or in the aqueous phase as dissolved and colloidal species. The scope is limited to consideration of degradation of the CSNF rods following an initial breach of the cladding. It considers features of CSNF that limit the availability of individual radionuclides for release into the gaseous or aqueous phases that may contact the fuel and the processes and events expected to degrade these CSNF features. In short, the purpose is to describe the characteristics of breached fuel rods and the degradation processes expected to influence radionuclide release

Characteristics of potential repository wastes

International Nuclear Information System (INIS)

1992-07-01

The LWR spent fuels discussed in Volume 1 of this report comprise about 99% of all domestic non-reprocessed spent fuel. In this report we discuss other types of spent fuels which, although small in relative quantity, consist of a number of diverse types, sizes, and compositions. Many of these fuels are candidates for repository disposal. Some non-LWR spent fuels are currently reprocessed or are scheduled for reprocessing in DOE facilities at the Savannah River Site, Hanford Site, and the Idaho National Engineering Laboratory. It appears likely that the reprocessing of fuels that have been reprocessed in the past will continue and that the resulting high-level wastes will become part of defense HLW. However, it is not entirely clear in some cases whether a given fuel will be reprocessed, especially in cases where pretreatment may be needed before reprocessing, or where the enrichment is not high enough to make reprocessing attractive. Some fuels may be canistered, while others may require special means of disposal. The major categories covered in this chapter include HTGR spent fuel from the Fort St. Vrain and Peach Bottom-1 reactors, research and test reactor fuels, and miscellaneous fuels, and wastes generated from the decommissioning of facilities

IMPROVEMENT OF THE PROCESSING OF SOLID WASTE IN UKRAINE

Directory of Open Access Journals (Sweden)

T. Kharchenko

2014-12-01

Full Text Available The article is dedicated to the problems of recycling and solid waste. It is investigated traditional methods of waste management (storage, disposal, incineration. Authors insist on ineffectiveness of these methods, because of the pollution increases anthropogenic pressure on the environment. It is proved harmful health effects using the traditional methods of disposal. The question of introducing innovative recycling, particularly separating solid waste, the development and use of clean technology waste processing, using microorganisms, pyrolysis. It is determined implementation barriers such as lack of effective government support, and high cost. It is noted that there is a problem of underestimating the complexity, scope and specifics of the issue. The experience of developed countries is outlined. The comparative performance of existing tariffs for disposal of solid waste is used. The ways of solving problems are done.

Characteristics of used CANDU fuel relevant to the Canadian nuclear fuel waste management program

Energy Technology Data Exchange (ETDEWEB)

Wasywich, K M

1993-05-01

Literature data on the characteristics of used CANDU power reactor fuel that are relevant to its performance as a waste form have been compiled in a convenient handbook. Information about the quantities of used fuel generated, burnup, radionuclide inventories, fission gas release, void volume and surface area, fuel microstructure, fuel cladding properties, changes in fuel bundle properties due to immobilization processes, radiation fields, decay heat and future trends is presented for various CANDU fuel designs. (author). 199 refs., 39 tabs., 100 figs.

Characteristics of used CANDU fuel relevant to the Canadian nuclear fuel waste management program

International Nuclear Information System (INIS)

Wasywich, K.M.

1993-05-01

Literature data on the characteristics of used CANDU power reactor fuel that are relevant to its performance as a waste form have been compiled in a convenient handbook. Information about the quantities of used fuel generated, burnup, radionuclide inventories, fission gas release, void volume and surface area, fuel microstructure, fuel cladding properties, changes in fuel bundle properties due to immobilization processes, radiation fields, decay heat and future trends is presented for various CANDU fuel designs. (author). 199 refs., 39 tabs., 100 figs

Characteristics of volatile compound emission and odor pollution from municipal solid waste treating/disposal facilities of a city in Eastern China

DEFF Research Database (Denmark)

Guo, Hanwen; Duan, Zhenhan; Zhao, Yan

2017-01-01

Transfer station, incineration plant, and landfill site made up the major parts of municipal solid waste disposal system of S city in Eastern China. Characteristics of volatile compounds (VCs) and odor pollution of each facility were investigated from a systematic perspective. Also major index...... in the waste tipping port of the incineration plant. A positive correlation between the olfactory and chemical odor concentrations was found with R2 = 0.918 (n = 15, P technology to deal...... with the non-source-separated waste. Strong attention thus needs to be paid on the enclosed systems in incineration plant to avoid any accidental odor emission....

Regulatory document R-104, Regulatory objectives, requirements and guidelines for the disposal of radioactive wastes - long-term aspects

International Nuclear Information System (INIS)

1987-01-01

The purpose and scope of this document is to present the regulatory basis for judging the long-term acceptability of radioactive waste disposal options. The basic objectives of radioactive waste disposal are given as are the regulatory requirements to be satisfied. (NEA)

Technical feasibility study on volumetric reduction of radioactive wastes using plasma technology

Energy Technology Data Exchange (ETDEWEB)

Prado, E.S.P.; Dellamano, J.C.; Carneiro, A.L.G.; Santos, R.C.; Potiens Junior, A.J. [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil); Petraconi, G., E-mail: edu.petraconi@usp.br [Instituto Tecnológico da Aeronáutica (ITA), São José dos Campos, SP (Brazil)

2017-07-01

The radioactive waste arising from nuclear reactors, hospitals, industry and research institutes are generated daily with a considerable amount. To final dispose of these radioactive waste safely and cost effectively, they must be transformed into physical and chemical compounds suitable for radionuclides immobilization with maximum volume and exhaust gaseous reduction. In this scope, among the promising technologies for the radioactive waste treatment, plasma technology allows reducing substantially the waste volume after exposing them to temperatures above 2,500 deg C. In the planning and management of radioactive waste, the challenges related to plasma technology are presented as a motivation factor for the possible implantation of plasma reactors in nuclear plants and research centers aiming at improving the process of radioactive waste management. (author)

Technical feasibility study on volumetric reduction of radioactive wastes using plasma technology

International Nuclear Information System (INIS)

Prado, E.S.P.; Dellamano, J.C.; Carneiro, A.L.G.; Santos, R.C.; Potiens Junior, A.J.; Petraconi, G.

2017-01-01

The radioactive waste arising from nuclear reactors, hospitals, industry and research institutes are generated daily with a considerable amount. To final dispose of these radioactive waste safely and cost effectively, they must be transformed into physical and chemical compounds suitable for radionuclides immobilization with maximum volume and exhaust gaseous reduction. In this scope, among the promising technologies for the radioactive waste treatment, plasma technology allows reducing substantially the waste volume after exposing them to temperatures above 2,500 deg C. In the planning and management of radioactive waste, the challenges related to plasma technology are presented as a motivation factor for the possible implantation of plasma reactors in nuclear plants and research centers aiming at improving the process of radioactive waste management. (author)

ERM 593 Applied Project_Guidance for Reviewing and Approving a Waste Stream Profile in the Waste Compliance and Tracking System_Final_05-05-15

Energy Technology Data Exchange (ETDEWEB)

Elicio, Andy U. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-05-05

My ERM 593 applied project will provide guidance for the Los Alamos National Laboratory Waste Stream Profile reviewer (i.e. RCRA reviewer) in regards to Reviewing and Approving a Waste Stream Profile in the Waste Compliance and Tracking System. The Waste Compliance and Tracking system is called WCATS. WCATS is a web-based application that “supports the generation, characterization, processing and shipment of LANL radioactive, hazardous, and industrial waste.” The LANL generator must characterize their waste via electronically by filling out a waste stream profile (WSP) in WCATS. Once this process is completed, the designated waste management coordinator (WMC) will perform a review of the waste stream profile to ensure the generator has completed their waste stream characterization in accordance with applicable state, federal and LANL directives particularly P930-1, “LANL Waste Acceptance Criteria,” and the “Waste Compliance and Tracking System User's Manual, MAN-5004, R2,” as applicable. My guidance/applied project will describe the purpose, scope, acronyms, definitions, responsibilities, assumptions and guidance for the WSP reviewer as it pertains to each panel and subpanel of a waste stream profile.

Quarterly Progress Report Research And Development Activities Waste Fixation Program October Through December 1976

International Nuclear Information System (INIS)

McElroy, J. L.

1977-01-01

Research and development activities of the Waste Fixation Program for October through December 1976 are described in this report. The objective of this program is to develop processes to convert high-level radioactive liquid waste (HLLW) to solid forms that are demonstrated to be physically, chemically, and radiolytically stable and inert. The scope of this program encompasses plans to make available a flexible advancing technology for the solidification of radioactive waste. Early technology will produce borosilicate glass by in-can melting and continuous electric melters. Multibarrier waste forms will be developed for future application

Neutralized current acid waste consolidation management plan

International Nuclear Information System (INIS)

Powell, W.J.; Brown, R.G.; Galbraith, J.; Jensen, C.; Place, D.E.; Reddick, G.W.; Zuroff, W.; Brothers, A.J.

1996-01-01

The scope of this evaluation is to recommend a management plan for the high-heat tank waste, including neutralized current acid waste (NCAW) in AY and AZ Tank Farms, and tank C-106 waste. The movement of solids, liquids and salt cake in the designated tank farms is included. Decision analysis techniques were used to determine a recommended alternative. The recommended course of action was replacement of a 75-hp mixer pump in tank AY-102 and in-tank concentration of tank AZ-102 supernate. The alternative includes transfer fo tank C-106 sludge to tank AY-102, then transfer to tank AY-102 and tank C-106 sludge to tank AZ-101 using the new 75-hp mixer pump installed in tank AY-102. Tank AZ-101 becomes a storage tank for high-level waste (HLW) sludge, with the capacity to mix and transfer sludge as desired

Full-scope training simulators

International Nuclear Information System (INIS)

Ugedo, E.

1986-01-01

The following topics to be covered in this report are: Reasons justifying the use of full-scope simulators for operator qualification. Full-scope simulator description: the control room, the physical models, the computer complex, the instructor's console. Main features of full-scope simulators. Merits of simulator training. The role of full-scope simulators in the training programs. The process of ordering and acquiring a full-scope simulator. Maintaining and updating simulator capabilities. (orig./GL)

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

International Nuclear Information System (INIS)

1991-01-01

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

Vitrified medical wastes bottom ash in cement clinkerization. Microstructural, hydration and leaching characteristics.

Science.gov (United States)

Papamarkou, S; Christopoulos, D; Tsakiridis, P E; Bartzas, G; Tsakalakis, K

2018-04-19

The present investigation focuses on the utilization of medical wastes incineration bottom ash (MBA), vitrified with soda lime recycled glass (SLRG), as an alternative raw material in cement clinkerization. Bottom ash is recovered from the bottom of the medical wastes incineration chamber, after being cooled down through quenching. It corresponds to 10-15 wt% of the initial medical wastes weight and since it has been classified in the category of hazardous wastes, its safe management has become a major environmental concern worldwide. MBA glasses of various syntheses were initially obtained during the MBA vitrification simultaneously with various amounts of silica scrap (20, 25 and 30 wt% correspondingly). The produced MBA glasses were in turn used for the production of Portland cement clinker, after sintering at 1400 °C, thus substituting traditional raw materials. Both evaluation of vitrification and sintering products was carried out by chemical and mineralogical analyses along with microstructure examination. The final cements were prepared by clinkers co-grinding in a laboratory ball mill with appropriate amounts of gypsum (≈5.0 wt%) and the evaluation of their quality was carried out by determining setting times, standard consistency, expansibility and compressive strength at 2, 7, 28 and 90 days. Finally, the leaching behaviour of the vitrified MBA and hydrated cements, together with the corresponding of the "as received" MBA, was further examined using the standard leaching tests of the Toxicity Characteristic Leaching Procedure (TCLP) and the EN 12457-2. According to the obtained results, the quality of the produced cement clinkers was not affected by the addition of the vitrified MBA in the raw meal, with the trace elements detected in all leachates measured well below the corresponding regulatory limits. Copyright © 2018 Elsevier B.V. All rights reserved.

Summary of radioactive solid waste received in the 200 Areas during calendar year 1993

International Nuclear Information System (INIS)

Anderson, J.D.; Hagel, D.L.

1994-09-01

Westinghouse Hanford Company manages and operates the Hanford Site 200 Areas radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Areas radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1993. This report does not include backlog waste, solid radioactive waste in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, ''Hanford Site Solid Waste Acceptance Criteria,'' (WHC 1988), liquid waste data are not included in this document

Mixed Waste Focus Area mercury contamination product line: An integrated approach to mercury waste treatment and disposal

International Nuclear Information System (INIS)

Hulet, G.A.; Conley, T.B.; Morris, M.I.

1998-01-01

The US Department of Energy (DOE) Mixed Waste Focus Area (MWFA) is tasked with ensuring that solutions are available for the mixed waste treatment problems of the DOE complex. During the MWFA's initial technical baseline development process, three of the top four technology deficiencies identified were related to the need for amalgamation, stabilization, and separation/removal technologies for the treatment of mercury and mercury-contaminated mixed waste. The focus area grouped mercury-waste-treatment activities into the mercury contamination product line under which development, demonstration, and deployment efforts are coordinated to provide tested technologies to meet the site needs. The Mercury Working Group (HgWG), a selected group of representatives from DOE sites with significant mercury waste inventories, is assisting the MWFA in soliciting, identifying, initiating, and managing efforts to address these areas. Based on the scope and magnitude of the mercury mixed waste problem, as defined by HgWG, solicitations and contract awards have been made to the private sector to demonstrate amalgamation and stabilization processes using actual mixed wastes. Development efforts are currently being funded under the product line that will address DOE's needs for separation/removal processes. This paper discusses the technology selection process, development activities, and the accomplishments of the MWFA to date through these various activities

Spent fuel and radioactive waste: an integrated data base of inventories, projections, and characteristics

International Nuclear Information System (INIS)

Notz, K.J.; Forsberg, C.W.; Mastal, E.F.

1984-01-01

The Integrated Data Base (IDB) Program provides official US Department of Energy (DOE) data on spent fuel and radioactive waste inventories, projections, and characteristics. This information is provided through the cooperative efforts of the IDB Program and DOE lead offices, lead sites, major programs, and generator sites. The program is entering its fifth year, and major accomplishments are summarized in three broad areas: (1) the annual inventory report, including ORIGEN2 applications and a Quality Assurance (QA) plan; (2) the summary data file and direct user access; and (3) data processing methodology and support to other programs. Plans for future work in these areas are outlined briefly, including increased utilization of personal computers. Some examples of spent fuel data are given in terms of projected quantities for two growth scenarios, burnup and age profile of the existing inventory, and the approximate specific thermal power relative to high-level waste (HLW) from various sources. 4 refs., 2 figs., 3 tabs

Third Finnish-German seminar on nuclear waste management 1986

International Nuclear Information System (INIS)

Lamberg, L.

1988-01-01

The scope of the seminar was to provide an interdisciplinary forum for exchange of information and experiences in the field of nuclear waste management. The highlights of the seminar focused on the following topics: overall reviews, waste products, nearfield phenomena, site investigations, performance assessment and decommissioning. All together 20 papers were presented. Reviews, status reports and experimental studies dealt with general research programs and current research and development activities including regulatory aspects. Extensive discussions provided and opportunity to identify issues and options for further research

Latin American forensic pathology: scope and needs

Directory of Open Access Journals (Sweden)

Gabriel M. Fonseca

2012-10-01

Full Text Available Pathology pertains to the study of a disease; from ancient times it has sought to explain the cause of death through postmortem examination. The advancement of science and technology has led to a greater definition of roles and has favored its development through different subspecialties among which we stands out forensic pathology. This discipline has its own characteristics, scope, case series, procedures and terminology. Likewise, although forensic pathology does not differ substantially from clinical pathology, significant differences can be found between the Anglo American approach and the Latin American approach. Beyond semantics of these alleged differences, the article reviews the concepts involved and discusses the scope and requirements needed to qualify experts, in the understanding that globalizing criteria should establish new paradigms and define the specific roles of the specialty.

Technical area status report for low-level mixed waste final waste forms

International Nuclear Information System (INIS)

Mayberry, J.L.; Huebner, T.L.; Ross, W.; Nakaoka, R.; Schumacher, R.; Cunnane, J.; Singh, D.; Darnell, R.; Greenhalgh, W.

1993-08-01

This report presents information on low-level mixed waste forms.The descriptions of the low-level mixed waste (LLMW) streams that are considered by the Mixed Waste Integrated Program (MWIP) are given in Appendix A. This information was taken from descriptions generated by the Mixed Waste Treatment Program (MWTP). Appendix B provides a list of characteristic properties initially considered by the Final Waste Form (FWF) Working Group (WG). A description of facilities available to test the various FWFs discussed in Volume I of DOE/MWIP-3 are given in Appendix C. Appendix D provides a summary of numerous articles that were reviewed on testing of FWFS. Information that was collected by the tests on the characteristic properties considered in this report are documented in Appendix D. The articles reviewed are not a comprehensive list, but are provided to give an indication of the data that are available

PROJECT SCOPE MANAGEMENT PROCESS

Directory of Open Access Journals (Sweden)

Yana Derenskaya

2018-01-01

Full Text Available The purpose of the article is to define the essence of project scope management process, its components, as well as to develop an algorithm of project scope management in terms of pharmaceutical production. Methodology. To carry out the study, available information sources on standards of project management in whole and elements of project scope management in particular are analysed. Methods of system and structural analysis, logical generalization are used to study the totality of subprocesses of project scope management, input and output documents, and to provide each of them. Methods of network planning are used to construct a precedence diagram of project scope management process. Results of the research showed that components of the project scope management are managing the scope of the project product and managing the content of project work. It is the second component is investigated in the presented work as a subject of research. Accordingly, it is defined that project scope management process is to substantiate and bring to the realization the necessary amount of work that ensures the successful implementation of the project (achievement of its goal and objectives of individual project participants. It is also determined that the process of managing the project scope takes into account the planning, definition of the project scope, creation of the structure of project work, confirmation of the scope and management of the project scope. Participants of these subprocesses are: customer, investor, and other project participants – external organizations (contractors of the project; project review committee; project manager and project team. It is revealed that the key element of planning the project scope is the formation of the structure of design work, the justification of the number of works, and the sequence of their implementation. It is recommended to use the following sequence of stages for creating the structure of project work

The review of radioactive waste management in the world

International Nuclear Information System (INIS)

Jalilzadeh, R.; Mirzahosseini, A.; Rahnomaei, N. A.

2008-01-01

Radioactive waste is generally classified on the basis of how much radiation and the type of radiation it emits as well as the length of time over which it will continue to emit radiation. Many activities dealing with radioactive materials produce nuclear wastes, including civilian nuclear power programs (nuclear Power plant operations and nuclear fuel-cycle activities), defense nuclear programs (nuclear weapons production, naval nuclear reactor programs, and related R and D), and industrial and institutional activities (scientific research, medical operations, and other industrial uses of Radioisotopic sources or Radio chemicals). To minimize the potential adverse health and environment impacts to people and other systems including of animals, plant and etc, during the entire lifetime of the radionuclides involved, nuclear waste must be carefully and properly managed. The scope of nuclear - waste management encompasses generation, processing (treatment and packaging), storage, transport, and disposal. in this research the effect of radioactive waste on environment and also disposal methods and radioactive waste management in countries is surveyed

Cross flow filtration of aqueous radioactive tank wastes

International Nuclear Information System (INIS)

McCabe, D.J.; Reynolds, B.A.; Todd, T.A.; Wilson, J.H.

1997-01-01

The Tank Focus Area (TFA) of the Department of Energy (DOE) Office of Science and Technology addresses remediation of radioactive waste currently stored in underground tanks. Baseline technologies for treatment of tank waste can be categorized into three types of solid liquid separation: (a) removal of radioactive species that have been absorbed or precipitated, (b) pretreatment, and (c) volume reduction of sludge and wash water. Solids formed from precipitation or absorption of radioactive ions require separation from the liquid phase to permit treatment of the liquid as Low Level Waste. This basic process is used for decontamination of tank waste at the Savannah River Site (SRS). Ion exchange of radioactive ions has been proposed for other tank wastes, requiring removal of insoluble solids to prevent bed fouling and downstream contamination. Additionally, volume reduction of washed sludge solids would reduce the tank space required for interim storage of High Level Wastes. The scope of this multi-site task is to evaluate the solid/liquid separations needed to permit treatment of tank wastes to accomplish these goals. Testing has emphasized cross now filtration with metal filters to pretreat tank wastes, due to tolerance of radiation and caustic

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

International Nuclear Information System (INIS)

Molecke, M.A.

1978-11-01

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

Engineering Scoping Study of Thermoelectric Generator Systems for Industrial Waste Heat Recovery

Energy Technology Data Exchange (ETDEWEB)

Hendricks, Terry [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Choate, William T. [BCS, Inc., Laurel, MD (United States)

2006-11-01

This report evaluates thermoelectric generator (TEG) systems with the intent to: 1) examine industrial processes in order to identify and quantify industrial waste heat sources that could potentially use TEGs; 2) describe the operating environment that a TEG would encounter in selected industrial processes and quantify the anticipated TEG system performance; 3) identify cost, design and/or engineering performance requirements that will be needed for TEGs to operate in the selected industrial processes; and 4) identify the research, development and deployment needed to overcome the limitations that discourage the development and use of TEGs for recovery of industrial waste heat.

Waste derived bioeconomy in India: A perspective.

Science.gov (United States)

S, Venkata Mohan; P, Chiranjeevi; Dahiya, Shikha; A, Naresh Kumar

2018-01-25

Environmental and climatic change issues, population explosion, rapid urbanisation, depletion of fossil reserves, need for energy security, huge waste generation, etc. are some of the inherent issues associated with the fossil based linear economy which need greater attention. In this context, the world is gradually transforming from fossil-based economy to a sustainable circular bio-economy. The biogenic waste which is generated in enormous quanties in India can be considered as potential feedstock for structuring the bio-based economy. This communication depicts the need for developing waste derived bioeconomy in the Indian perspective. Waste is now being perceived as a resource with value and believed to supplement petroleum feedstock to a great extent if properly utilized. The necessity to introduce waste as the core element for the future economic models which also allows sustainable development is discussed. The review also establishes drivers for the bioeconomy and structures the waste derived bioeconomy in a sustainable format to address the futuristic needs, scope and opportunities envisaged in the business and economic realm. The enabling technologies/processes that can be applied for biogenic wastes valorisation are elaborated. Circularizing the economy in a waste biorefinery model for the production of biobased products including bioenergy is discussed. Copyright © 2017 Elsevier B.V. All rights reserved.

Gasification experience with biomass and wastes

Energy Technology Data Exchange (ETDEWEB)

Schiffer, H P; Adlhoch, W [Rheinbraun AG, Cologne (Germany)

1997-12-31

The HTW process is particularly favourable for the gasification of low-rank feedstocks. During various tests - performed in b-bench- scale, pilot-scale and industrial scale units - consequences with regard to feedstock preparation. Gasification behaviour, corrosion, emission and residual matter were carefully studied for a large number of different feedstocks. Information is now available for optimal utilisation of several types of biomass and waste materials in relation to plant operation, emission and residue utilization. Different types of biomass were tested in bench-scale conditions in an atmospheric HTW process development unit. Industrial-scale experience concerning biomass is available from the Gasification plant at Oulu, Finland, which operated from 1988 to 1991, producing ammonia synthesis gas from dried Finnish peat. During several test campaigns performed at the HTW demonstration plant sewage sludge, loaded coke and used plastics were co-gasified at feeding rates of up to 5 t/h. Operability, conversion efficiency, syngas contaminants, solid residue characteristics and emissions were monitored very carefully. Co-gasification in a dried lignite mixture allows synthesis gas for methanol production to be obtained also from waste materials. Thus, waste is converted into a useful chemical feedstock. For both sewage sludge and loaded coke, conversion efficiency and syngas yield were sufficient. Within the scope of a solid residue characterization various contaminants, including chlorine, sulphur, heavy metals and other trace elements or organic compounds, their formation and/or release were detected. Emissions were well below the limits. However, an increase in the benzene and naphthalene concentrations in the crude gas occurred. Thus, a commercial application requires additional gas treatment. In the next few years, feedstock recycling of mixed plastics household waste from Duales System Deutschland GmbH will call for a plant capacity of 350 000 to 400 000

Gasification experience with biomass and wastes

Energy Technology Data Exchange (ETDEWEB)

Schiffer, H.P.; Adlhoch, W. [Rheinbraun AG, Cologne (Germany)

1996-12-31

The HTW process is particularly favourable for the gasification of low-rank feedstocks. During various tests - performed in b-bench- scale, pilot-scale and industrial scale units - consequences with regard to feedstock preparation. Gasification behaviour, corrosion, emission and residual matter were carefully studied for a large number of different feedstocks. Information is now available for optimal utilisation of several types of biomass and waste materials in relation to plant operation, emission and residue utilization. Different types of biomass were tested in bench-scale conditions in an atmospheric HTW process development unit. Industrial-scale experience concerning biomass is available from the Gasification plant at Oulu, Finland, which operated from 1988 to 1991, producing ammonia synthesis gas from dried Finnish peat. During several test campaigns performed at the HTW demonstration plant sewage sludge, loaded coke and used plastics were co-gasified at feeding rates of up to 5 t/h. Operability, conversion efficiency, syngas contaminants, solid residue characteristics and emissions were monitored very carefully. Co-gasification in a dried lignite mixture allows synthesis gas for methanol production to be obtained also from waste materials. Thus, waste is converted into a useful chemical feedstock. For both sewage sludge and loaded coke, conversion efficiency and syngas yield were sufficient. Within the scope of a solid residue characterization various contaminants, including chlorine, sulphur, heavy metals and other trace elements or organic compounds, their formation and/or release were detected. Emissions were well below the limits. However, an increase in the benzene and naphthalene concentrations in the crude gas occurred. Thus, a commercial application requires additional gas treatment. In the next few years, feedstock recycling of mixed plastics household waste from Duales System Deutschland GmbH will call for a plant capacity of 350 000 to 400 000

Functional specifications for a radioactive waste decision support system

International Nuclear Information System (INIS)

Westrom, G.B.; Kurrasch, E.R.; Carlton, R.E.; Vance, J.N.

1989-09-01

It is generally recognized that decisions relative to the treatment, handling, transportation and disposal of low-level wastes produced in nuclear power plants involve a complex array of many inter-related elements or considerations. Complex decision processes can be aided through the use of computer-based expert systems which are based on the knowledge of experts and the inferencing of that knowledge to provide advice to an end-user. To determine the feasibility of developing and applying an expert system in nuclear plant low level waste operations, a Functional Specification for a Radwaste Decision Support System (RDSS) was developed. All areas of radwaste management, from the point of waste generation to the disposition of the waste in the final disposal location were considered for inclusion within the scope of the RDSS. 27 figs., 8 tabs

Radioactive waste management. Response by the Town and Country Planning Association to the white paper 'Radioactive Waste Management' - Cmnd 8607

International Nuclear Information System (INIS)

1982-12-01

Technical, ethical, social, political and organizational aspects of the management of low-, intermediate-, and high-level radioactive wastes arising from operations in the United Kingdom are discussed. Recommendations are made to provide scope for public discussion, to consult the appropriate local water and other authorities, and to take other specified actions relevant to town and country planning. (U.K.)

Computer-aided waste management strategic planning and analysis

International Nuclear Information System (INIS)

Avci, H.I.; Kotek, T.J.; Koebnick, B.L.

1995-01-01

A computational model called WASTE-MGMT has been developed to assist in the evaluation of alternative waste management approaches in a complex setting involving multiple sites, waste streams, and processing options. The model provides the quantities and characteristics of wastes processed at any facility or shipped between any two sites as well as environmental emissions at any facility within the waste management system. The model input is defined by three types of fundamental waste management data: (1) waste inventories and characteristics at the point of generation; (2) treatment, storage, and disposal facility characteristics; and (3) definitions of alternative management approaches. The model has been successfully used in the preparation of the US Department of Energy (DOE) Environmental Management Programmatic.Environmental Impact Statement (EM PEIS). Certain improvements are either being implemented or planned that would extend the usefulness and applicability of the WASTE-MGMT model beyond the EM PEIS and info the. strategic planning for management of wastes under the responsibility of DOE or other agencies

Characterization of civil construction waste and its incorporation to mortar

International Nuclear Information System (INIS)

Cunha, G.A.; Andrade, A.C.D.; Souza, J.M.M.; Evangelista, A.C.J.; Almeida, V.C.

2009-01-01

As the preservation of the environment is a big concern nowadays, plenty of studies have arisen in order to decrease the production or reuse the waste from human activities. In this context, the civil construction industry comes up, as it is able to incorporate waste to mortar, being a great alternative for the reuse of solid waste. The scope of this work has been the characterization of Construction and Demolishment Waste (RCD) and its incorporation to the mortar aiming at the development of alternative construction materials in the future for the economical reutilization of waste discharged in embankments and landfills so far preserving the environment so far. The experimental studies taken with sample bodies, such as water absorption, resistance to compression, X-ray diffraction, X-ray fluorescence and scanning electronic microscopy, elicits the viability of the partial substitution of cement by RCD mixed waste, taking its different applications into consideration. (author)

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

International Nuclear Information System (INIS)

Claghorn, R.D.

1998-01-01

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

Waste Package Design Methodology Report

Energy Technology Data Exchange (ETDEWEB)

D.A. Brownson

2001-09-28

The objective of this report is to describe the analytical methods and processes used by the Waste Package Design Section to establish the integrity of the various waste package designs, the emplacement pallet, and the drip shield. The scope of this report shall be the methodology used in criticality, risk-informed, shielding, source term, structural, and thermal analyses. The basic features and appropriateness of the methods are illustrated, and the processes are defined whereby input values and assumptions flow through the application of those methods to obtain designs that ensure defense-in-depth as well as satisfy requirements on system performance. Such requirements include those imposed by federal regulation, from both the U.S. Department of Energy (DOE) and U.S. Nuclear Regulatory Commission (NRC), and those imposed by the Yucca Mountain Project to meet repository performance goals. The report is to be used, in part, to describe the waste package design methods and techniques to be used for producing input to the License Application Report.

Waste Package Design Methodology Report

International Nuclear Information System (INIS)

D.A. Brownson

2001-01-01

The objective of this report is to describe the analytical methods and processes used by the Waste Package Design Section to establish the integrity of the various waste package designs, the emplacement pallet, and the drip shield. The scope of this report shall be the methodology used in criticality, risk-informed, shielding, source term, structural, and thermal analyses. The basic features and appropriateness of the methods are illustrated, and the processes are defined whereby input values and assumptions flow through the application of those methods to obtain designs that ensure defense-in-depth as well as satisfy requirements on system performance. Such requirements include those imposed by federal regulation, from both the U.S. Department of Energy (DOE) and U.S. Nuclear Regulatory Commission (NRC), and those imposed by the Yucca Mountain Project to meet repository performance goals. The report is to be used, in part, to describe the waste package design methods and techniques to be used for producing input to the License Application Report

Remedial action and waste disposal project -- 300-FF-1 remedial action readiness assessment report

International Nuclear Information System (INIS)

Carson, J.W.; Carlson, R.A.; Greif, A.A.; Johnson, C.R.; Orewiler, R.I.; Perry, D.M.; Remsen, W.E.; Tuttle, B.G.; Wilson, R.C.

1997-09-01

This report documents the readiness assessment for initial startup of the 300-FF-1 Remedial Action Task. A readiness assessment verifies and documents that field activities are ready to start (or restart) safely. The 300-FF-1 assessment was initiated in April 1997. Readiness assessment activities included confirming the completion of project-specific procedures and permits, training staff, obtaining support equipment, receipt and approval of subcontractor submittals, and mobilization and construction of site support systems. The scope of the 300-FF-1 Remedial Action Task includes excavation and disposal of contaminated soils at liquid waste disposal facilities and of waste in the 618-4 Burial Ground and the 300-FF-1 landfills. The scope also includes excavation of test pits and test trenches

Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

D'Amico, E. L; Edmiston, D. R.; O'Leary, G. A.; Rivera, M. A.; Steward, D. M.

2006-01-01

In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

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

International Nuclear Information System (INIS)

PRIGNANO, A.L.

2000-01-01

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

Radioactive Waste Management In The Chernobyl Exclusion Zone - 25 Years Since The Chernobyl Nuclear Power Plant Accident

International Nuclear Information System (INIS)

Farfan, E.; Jannik, T.

2011-01-01

Radioactive waste management is an important component of the Chernobyl Nuclear Power Plant accident mitigation and remediation activities of the so-called Chernobyl Exclusion Zone. This article describes the localization and characteristics of the radioactive waste present in the Chernobyl Exclusion Zone and summarizes the pathways and strategy for handling the radioactive waste related problems in Ukraine and the Chernobyl Exclusion Zone, and in particular, the pathways and strategies stipulated by the National Radioactive Waste Management Program. The brief overview of the radioactive waste issues in the ChEZ presented in this article demonstrates that management of radioactive waste resulting from a beyond-designbasis accident at a nuclear power plant becomes the most challenging and the costliest effort during the mitigation and remediation activities. The costs of these activities are so high that the provision of radioactive waste final disposal facilities compliant with existing radiation safety requirements becomes an intolerable burden for the current generation of a single country, Ukraine. The nuclear accident at the Fukushima-1 NPP strongly indicates that accidents at nuclear sites may occur in any, even in a most technologically advanced country, and the Chernobyl experience shows that the scope of the radioactive waste management activities associated with the mitigation of such accidents may exceed the capabilities of a single country. Development of a special international program for broad international cooperation in accident related radioactive waste management activities is required to handle these issues. It would also be reasonable to consider establishment of a dedicated international fund for mitigation of accidents at nuclear sites, specifically, for handling radioactive waste problems in the ChEZ. The experience of handling Chernobyl radioactive waste management issues, including large volumes of radioactive soils and complex structures

Long-term durability experiments with concrete-based waste packages in simulated repository conditions

International Nuclear Information System (INIS)

Ipatti, A.

1993-03-01

Two extensive experiments on long-term durability of waste packages in simulated repository conditions are described. The first one is a 'half-scale experiment' comprising radioactive waste product and half-scale concrete containers in site specific groundwater conditions. The second one is 'full-scale experiment' including simulated inactive waste product and full-scale concrete container stored in slowly flowing fresh water. The scope of the experiments is to demonstrate long-term behaviour of the designed waste packages in contact with moderately concrete aggressive groundwater, and to evaluate the possible interactions between the waste product, concrete container and ground water. As the waste packages are made of high-quality concrete, provisions have been made to continue the experiments for several years

Relation between leaching characteristics of heavy metals and physical properties of fly ashes from typical municipal solid waste incinerators.

Science.gov (United States)

Ni, Peng; Li, Hailong; Zhao, Yongchun; Zhang, Junying; Zheng, Chuguang

2017-09-01

Due to the alkalinity and high concentration of potentially hazardous heavy metals, fly ash from a municipal solid waste (MSW) incinerator is classified as hazardous waste, which should be of particular concern. Physical and chemical characterizations of the contrasted fly ashes were investigated to explore the relation between leaching characteristics of heavy metals and physical properties of fly ashes. The results showed that CaClOH, NaCl, Ca(OH) 2 , KCl and SiO 2 were primary mineral compositions in the MSWI fly ashes, and the particle size distribution of fly ash ranged between 10 μm and 300 μm. The smaller the particle size distribution of fly ash, the larger the BET-specific surface area, which was beneficial to the leaching of heavy metals. As a result of various pores, it easily accumulated heavy metals as well. The leaching tests exhibited a high leachability of heavy metals and the leaching concentration of Pb in almost all of the fly ash samples went far beyond the Standard for Pollution Control on the Landfill Site of Municipal Solid Waste. Thereupon, it is necessary to establish proper disposal systems and management strategies for environmental protection based on the characteristics of MSW incineration (MSWI) fly ash in China.

Waste Feed Delivery Planning at Hanford - 13232

International Nuclear Information System (INIS)

Certa, Paul J.; Hohl, Ted M.; Kelly, James W.; Larsen, Douglas C.; West, Elizha B.; Ritari, Jaakob S.; Rodriguez, Juissepp S.

2013-01-01

The Integrated Waste Feed Delivery Plan (IWFDP) describes how waste feed will be delivered to the Waste Treatment and Immobilization Plant (WTP) to safely and efficiently accomplish the River Protection Project (RPP) mission. The IWFDP, which is integrated with the Baseline Case operating scenario, is comprised of three volumes. Volume 1 - Process Strategy provides an overview of waste feed delivery (WFD) and describes how the WFD system will be used to prepare and deliver feed to the WTP based on the equipment configuration and functional capabilities of the WFD system. Volume 2 - Campaign Plan describes the plans for the first eight campaigns for delivery to the WTP, evaluates projected feed for systematic issues, projects 242-A Evaporator campaigns, and evaluates double-shell tank (DST) space and availability of contingency feed. Volume 3 - Project Plan identifies the scope and timing of the DST and infrastructure upgrade projects necessary to feed the WTP, and coordinates over 30 projectized projects and operational activities that comprise the needed WFD upgrades. (authors)

Waste Feed Delivery Planning at Hanford - 13232

Energy Technology Data Exchange (ETDEWEB)

Certa, Paul J.; Hohl, Ted M.; Kelly, James W.; Larsen, Douglas C.; West, Elizha B.; Ritari, Jaakob S.; Rodriguez, Juissepp S. [Washington River Protection Solutions, LLC, P.O. 850, Richland, WA 99352 (United States)

2013-07-01

The Integrated Waste Feed Delivery Plan (IWFDP) describes how waste feed will be delivered to the Waste Treatment and Immobilization Plant (WTP) to safely and efficiently accomplish the River Protection Project (RPP) mission. The IWFDP, which is integrated with the Baseline Case operating scenario, is comprised of three volumes. Volume 1 - Process Strategy provides an overview of waste feed delivery (WFD) and describes how the WFD system will be used to prepare and deliver feed to the WTP based on the equipment configuration and functional capabilities of the WFD system. Volume 2 - Campaign Plan describes the plans for the first eight campaigns for delivery to the WTP, evaluates projected feed for systematic issues, projects 242-A Evaporator campaigns, and evaluates double-shell tank (DST) space and availability of contingency feed. Volume 3 - Project Plan identifies the scope and timing of the DST and infrastructure upgrade projects necessary to feed the WTP, and coordinates over 30 projectized projects and operational activities that comprise the needed WFD upgrades. (authors)

Waste feed delivery planning at Hanford-13232

International Nuclear Information System (INIS)

Certa, Paul J.; West, Elizha B.; Rodriguez, Juissepp S.; Hohl, Ted M.; Larsen, Douglas C.; Ritari, Jaakob S.; Kelly, James W.

2013-01-01

The Integrated Waste Feed Delivery Plan (IWFDP) describes how waste feed will be delivered to the Waste Treatment and Immobilization Plant (WTP) to safely and efficiently accomplish the River Protection Project (RPP) mission. The IWFDP, which is integrated with the Baseline Case operating scenario, is comprised of three volumes. Volume 1 - Process Strategy provides an overview of waste feed delivery (WFD) and describes how the WFD system will be used to prepare and deliver feed to the WTP based on the equipment configuration and functional capabilities of the WFD system. Volume 2 - Campaign Plan describes the plans for the first eight campaigns for delivery to the WTP, evaluates projected feed for systematic issues, projects 242-A Evaporator campaigns, and evaluates double-shell tank (DST) space and availability of contingency feed. Volume 3 - Project Plan identifies the scope and timing of the DST and infrastructure upgrade projects necessary to feed the WTP, and coordinates over 30 projectized projects and operational activities that comprise the needed WFD upgrades

Influence of injection timing on DI diesel engine characteristics fueled with waste transformer oil

Directory of Open Access Journals (Sweden)

S. Prasanna Raj Yadav

2015-12-01

Full Text Available This research work targets on the effective utilization of WTO (waste transformer oil in a diesel engine, which would rather reduce environmental problems caused by disposing of it in the open land. The waste transformer oil was compared with the conventional diesel fuel and found that it can also be used as fuel in compression ignition engines since the WTO is also a derivative of crude oil. In this present work, the WTO has been subjected to traditional base-catalyzed trans-esterification process in order to reduce the high viscosity of the WTO which helps to effectively utilize WTO as a fuel in DI diesel engine. The objective of the work is to study the influence of injection timing on the performance, emission and combustion characteristics of a single cylinder, four stroke, direct injection diesel engine using TWTO (trans-esterified waste transformer oil as a fuel. Experiments were performed at four injection timings (23°, 22°, 21°, and 20° bTDC. The results indicate that the retarded injection timing of 20° bTDC resulted in decreased oxides of nitrogen, carbon monoxide and unburned hydrocarbon by 11.57%, 17.24%, and 10% respectively while the brake thermal efficiency and smoke increased under all the load conditions when compared to that of standard injection timing.

Radioactive waste management in the former USSR. Volume 3

Energy Technology Data Exchange (ETDEWEB)

Bradley, D.J.

1992-06-01

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world`s largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

Hydrogeological characteristics of Beishan preselected area, Gansu province for China's high-level radioactive waste repository

International Nuclear Information System (INIS)

Guo Yonghai; Yang Tianxiao; Liu Shufen

2001-01-01

Groundwater is the major carrier for radionuclide migration in the high-level radioactive waste disposal. For this reason the hydrogeological study is one of the main contents in repository siting. According to the field investigation which has been carried out during the last few years and some data from the previous study, the author describes the general hydrogeological situation and groundwater circulation, as well as chemical characteristics of groundwater in Beishan preselected area, Gansu province. The research shows that main hydrogeological characteristics of the Beishan area is water-bearing character, low permeability and slow water movement while the major chemical feature of groundwater is high mineralization. This recognition will provide an important basis for repository siting in the site area

Summary of radioactive solid waste received in the 200 areas during calendar year 1997

International Nuclear Information System (INIS)

Hagel, D.L.

1998-01-01

Waste Management Federal Services of Hanford Inc. manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office under contract DE-AC06-87RL10930. These facilities include storage areas and disposal sites for radioactive solid waste. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1997. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Cafeteria, liquid waste data are not included in this document

Summary of radioactive solid waste received in the 200 Areas during calendar year 1992

International Nuclear Information System (INIS)

Anderson, J.D.; Hagel, D.L.

1992-05-01

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1991. This report does not include solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms, or backlog wastes. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, (WHC 1988), liquid waste data are not included in this document

Summary of radioactive solid waste received in the 200 Areas during calendar year 1994

International Nuclear Information System (INIS)

Anderson, J.D.; Hagel, D.L.

1995-08-01

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive material that has been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1994. This report does not include backlog waste: solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria (WHC 1988), liquid waste data are not included in this document

Summary of radioactive solid waste received in the 200 Areas during calendar year 1994

Energy Technology Data Exchange (ETDEWEB)

Anderson, J.D.; Hagel, D.L.

1995-08-01

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive material that has been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1994. This report does not include backlog waste: solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria (WHC 1988), liquid waste data are not included in this document.

Summary of radioactive solid waste received in the 200 areas during calendar year 1997

Energy Technology Data Exchange (ETDEWEB)

Hagel, D.L.

1998-06-25

Waste Management Federal Services of Hanford Inc. manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office under contract DE-AC06-87RL10930. These facilities include storage areas and disposal sites for radioactive solid waste. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1997. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Cafeteria, liquid waste data are not included in this document.

The characterization of cement waste form for final disposal of decommissioning concrete wastes

International Nuclear Information System (INIS)

Lee, Yoon-ji; Lee, Ki-Won; Min, Byung-Youn; Hwang, Doo-Seong; Moon, Jei-Kwon

2015-01-01

Highlights: • Decommissioning concrete waste recycling and disposal. • Compressive strength of cement waste form. • Characteristic of thermal resistance and leaching of cement waste form. - Abstract: In Korea, the decontamination and decommissioning of KRR-1, 2 at KAERI have been under way. The decommissioning of the KRR-2 was finished completely by 2011, whereas the decommissioning of KRR-1 is currently underway. A large quantity of slightly contaminated concrete waste has been generated from the decommissioning projects. The concrete wastes, 83ea of 200 L drums, and 41ea of 4 m 3 containers, were generated in the decommissioning projects. The conditioning of concrete waste is needed for final disposal. Concrete waste is conditioned as follows: mortar using coarse and fine aggregates is filled with a void space after concrete rubble pre-placement into 200 L drums. Thus, this research developed an optimizing mixing ratio of concrete waste, water, and cement, and evaluated the characteristics of a cement waste form to meet the requirements specified in the disposal site specific waste acceptance criteria. The results obtained from a compressive strength test, leaching test, and thermal cycling test of cement waste forms conclude that the concrete waste, water, and cement have been suggested as an optimized mixing ratio of 75:15:10. In addition, the compressive strength of the cement waste form was satisfied, including a fine powder up to a maximum of 40 wt% in concrete debris waste of about 75%. According to the scale-up test, the mixing ratio of concrete waste, water, and cement is 75:10:15, which meets the satisfied compressive strength because of an increase in the particle size in the waste