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Ocean disposal option for bulk wastes containing naturally occurring radionuclides: an assessment case history. [From Niagara Falls storage site]

Description: There are 180,000 m/sup 3/ of slightly contaminated radioactive wastes (36 pCi/g radium-226) currently stored at the US Department of Energy's Niagara Falls Storage Site (NFSS), near Lewiston, New York. These wastes resulted from the cleanup of soils that were contaminated above the guidelines for unrestricted use of property. An alternative to long-term management of these wastes on land is dispersal in the ocean. A scenario for ocean disposal is present
Date: January 1, 1985
Creator: Stull, E.A. & Merry-Libby, P.
Partner: UNT Libraries Government Documents Department

Guidelines for developing certification programs for newly generated TRU waste

Description: These guidelines were prepared with direction from the US Department of Energy (DOE) Transuranic (TRU) Waste Management Program in support of the DOE effort to certify that newly generated TRU wastes meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria. The guidelines provide instructions for generic Certification Program preparation for TRU-waste generators preparing site-specific Certification Programs in response to WIPP requirements. The guidelines address all major aspects of a Certification Program that are necessary to satisfy the WIPP Waste Acceptance Criteria and their associated Compliance Requirements and Certification Quality Assurance Requirements. The details of the major element of a Certification Program, namely, the Certification Plan, are described. The Certification Plan relies on supporting data and control documentation to provide a traceable, auditable account of certification activities. Examples of specific parts of the Certification Plan illustrate the recommended degree of detail. Also, a brief description of generic waste processes related to certification activities is included.
Date: May 1, 1983
Creator: Whitty, W.J.; Ostenak, C.A.; Pillay, K.K.S. & Geoffrion, R.R.
Partner: UNT Libraries Government Documents Department

Office of Waste Isolation progress report, December 1977

Description: This document reports progress on the OWI's portion of the National Waste Terminal Storage (NWTS) program. It comprises project reports on work performed by organizations under subcontract to OWI, by DOE contractors, by OWI consultants, and by other federal agencies participating in the NWTS program. They are made under the headings technical projects, facility projects, planning and analysis, and regulatory affairs. (DLC)
Date: January 31, 1976
Creator: Zerby, C.D.
Partner: UNT Libraries Government Documents Department

Office of Waste Isolation progress report, January 1978

Description: This document, prepared to report progress on the National Waste Terminal Storage (NWTS) program, consists of project reports on work performed by organizations under subcontract to OWI, by DOE contractors, by OWI consultants, and by other federal agencies participating in the NWTS program. The project reports are made under the headings technical projects, facility projects, planning and analysis, and regulatory affairs. (DLC)
Date: February 28, 1978
Creator: Zerby, C.D.
Partner: UNT Libraries Government Documents Department

Evaluation of the IRAD sonic extensometers for application in the Canadian Underground Research Laboratory (FY 1983)

Description: This report supplements an earlier study that discussed the suitability of using the IRAD sonic extensometer in the Underground Research Laboratory proposed by the Atomic Energy of Canada, Ltd. In particular, it addresses the first and fourth recommendations made in that report concerning the basic accuracy of the instrument and evaluation of the electronic circuitry, respectively.
Date: September 1, 1983
Creator: Glenn, H.D. & Butler, L.S.
Partner: UNT Libraries Government Documents Department

Test plan: Potash Core Test. WIPP experimental program borehole plugging

Description: The Potash Core Test will utilize a WIPP emplaced plug to obtain samples of an in-situ cured plug of known mix constituents for bench scale testing. An earlier effort involved recovery at the salt horizon of Plug 217, a 17 year old plug in a potash exploration hole for bond testing, but the lack of particulars in the emplacement precluded significant determination of plug performance.
Date: September 1, 1979
Creator: Christensen, C.L.
Partner: UNT Libraries Government Documents Department

Regulatory requirements important to Hanford single-shell tank waste management decisions

Description: This report provides an initial analysis of the regulations that may be pertinent to SST management activities (e.g., characterization, disposal, retrieval, processing, etc.) and the interrelationships among those regulations. Waste disposal decisions regarding SST waste must consider the regulatory requirements against which technical solutions will be evaluated. Regulatory requirements can also be used as guidelines for management and disposal of waste in a manner that protects human health and safety and the environment. Also, in cases where waste management regulations do not specifically address a waste form, such as radioactive mixed waste, the SST waste may come under the purview of a number of regulations related to radioactive waste management, hazardous waste management, and water and air quality protection. This report provides a comprehensive review of the environmental pollution control and radioactive waste management statutes and regulations that are relevant to SST waste characterization and management. Also, other statutes and regulations that contain technical standards that may be used in the absence of directly applicable regulations are analyzed. 8 refs., 4 figs.
Date: June 1, 1989
Creator: Keller, J.F.; Woodruff, M.G.; Schmidt, A.J.; Hendrickson, P.L. & Selby, K.B.
Partner: UNT Libraries Government Documents Department

Technology transfer in hazardous waste management

Description: Hazardous waste is a growing problem in all parts of the world. Industrialized countries have had to deal with the treatment and disposal of hazardous wastes for many years. The newly industrializing countries of the world are now faced with immediate problems of waste handling. The developing nations of the world are looking at increasing quantities of hazardous waste generation as they move toward higher levels of industrialization. Available data are included on hazardous waste generation in Asia and the Pacific as a function of Gross Domestic Product (GDP). Although there are many inconsistencies in the data (inconsistent hazardous waste definitions, inconsistent reporting of wastes, etc.) there is definite indication that a growing economy tends to lead toward larger quantities of hazardous waste generation. In developing countries the industrial sector is growing at a faster rate than in the industrialized countries. In 1965 industry accounted for 29% of GDP in the developing countries of the world. In 1987 this had grown to 37% of GDP. In contrast, industry accounted for 40% of GDP in 1965 in industrialized countries and dropped to 35% in 1987. This growth in industrial activity in the developing countries brings an increase in the need to handle hazardous wastes. Although hazardous wastes are ubiquitous, the control of hazardous wastes varies. The number of regulatory options used by various countries in Asia and the Pacific to control wastes are included. It is evident that the industrialized countries, with a longer history of having to deal with hazardous wastes, have found the need to use more mechanisms to control them. 2 refs., 2 figs.
Date: January 1, 1989
Creator: Drucker, H.
Partner: UNT Libraries Government Documents Department

Fractal characteristics of fracture roughness and aperture data

Description: In this study mathematical expressions are developed for the characteristics of apertures between rough surfaces. It has shown that the correlation between the opposite surfaces influences the aperture properties and different models are presented for these different surface correlations. Fracture and apertures profiles measured from intact fractures are evaluated and it is found that they qualitatively follow the mathematically predicted trends.
Date: May 1, 1991
Creator: Kumar, S. (Polytechnic Inst. of Brooklyn, NY (United States). Dept. of Mechanical Engineering); Bodvarsson, G.S. (Lawrence Berkeley Lab., CA (United States)) & Boernge, J. (Bureau of Reclamation, Denver, CO (United States))
Partner: UNT Libraries Government Documents Department

Proposed format and content of environmental reports for deep geologic terminal repositories for radioactive material

Description: As the Nuclear Regulatory Commission has not yet issued a format guide for the preparation of an environmental impact statement for radioactive waste repositories, Rockwell Hanford operations has developed an annotated outline which will serve as the basis for the environmental evaluation activities until replaced by an appropriate NRC regulatory guide. According to the outline, the applicant should summarize the major environmental effects that are expected to occur during the construction, operation, and terminal isolation phases of the radioactive material repository. Compare these environmental effects with the possible effect of continued use of interim storage facilities. Unless unforeseen environmental effects become apparent, the summary should be a positive statement indicating that the short-term environmental effects are outweighed by the long-term benefits of the repository. (JSR)
Date: October 13, 1978
Creator: Carrell, D.J. & Jones, G.L.
Partner: UNT Libraries Government Documents Department

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 3A. GSFLS technical analysis (appendix). Interim report

Description: This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. The technical and financial considerations underlying a global spent fuel logistics systems have been studied and are reported. The Pacific Basin is used as a model throughout this report; however the stated methodology and, in many cases, considerations and conclusions are applicable to other global regions. Spent fuel discharge profiles for Pacific Basin Countries were used to determine the technical systems requirements for alternative concepts. Functional analyses and flows were generated to define both system design requirements and logistics parameters. A technology review was made to ascertain the state-of-the-art of relevant GSFLS technical systems. Modular GSFLS facility designs were developed using the information generated from the functional analysis and technology review. The modular facility designs were used as a basis for siting and cost estimates for various GSFLS alternatives. Various GSFLS concepts were analyzed from a financial and economic perspective in order to provide total concepts costs and ascertain financial and economic sensitivities to key GSFLS variations. Results of the study include quantification of GSFLS facility and hardware requirements; drawings of relevant GSFLS facility designs; system cost estimates; financial reports - including user service charges; and comparative analyses of various GSFLS alternatives.
Date: January 31, 1978
Creator: ,
Partner: UNT Libraries Government Documents Department

Proceedings of the first thermomechanical workshop for shale

Description: Chapter 2 provides a description of the three federal regulations that pertain to the development of a high-level nuclear waste repository regardless of the rock type. Chapter 3 summarizes the reference shale repository conditions selected for this workshop. A room-and-pillar configuration was considered at an extraction ratio of about 0.25. The depth was assumed to be 700 m. Chapter 4 gives a summary of several case histories that were considered to be valuable in gaining an understanding of some of the design and construction features that might be unique in creating underground openings in shale. Chapter 5 assesses the data and information needs, availability, technology for acquisition, and the research and development necessary for analytical/numerical modeling in heat transfer, fluid flow, and thermomechanics. Chapter 6 assesses data and information needs in the laboratory and considerations associated with shale rock characterization. Chapter 7 assesses the data and information needs, availability, technology for acquisition, and the research and development necessary for field/in situ testing. Chapter 8 presents the consensus of the workshop participants that there is a definite need to advance the state of knowledge concerning the thermomechanical behavior of shales and to gain experience in applying this knowledge to the design of room-and-pillar excavations. Finally, Chapter 9 provides a summary of the research and development needs in the various interacting activities of repository development, including analytical/numerical modeling, laboratory testing, and field/in situ testing. The main conclusion of the workshop was that a need exists for an aggressive program in laboratory, field, numerical modeling, and design studies to provide a thermomechanical, technological base for comparison of shale types and shale regions/areas/sites.
Date: March 1, 1986
Partner: UNT Libraries Government Documents Department

National waste terminal storage program: configuration management plan. Volume I. Management summary

Description: Objective of the Configuration Management Plan is to describe the Office of Waste Isolation's approach for the systematic identification, change control, status accounting, and auditing of: documents defining the NWTS Program and the plans for attaining the defined objectives; physical and functional characteristics of each storage site, facility, systems and equipment; and associated costs and schedules.
Date: May 1, 1977
Partner: UNT Libraries Government Documents Department

State of the art review of alternatives to shallow land burial of low level radioactive waste

Description: A review of alternatives to shallow land burial for disposal of low level radioactive waste was conducted to assist ORNL in developing a program for the evaluation, selection, and demonstration of the most acceptable alternatives. The alternatives were categorized as follows: (1) near term isolation concepts, (2) far term isolation concepts, (3) dispersion concepts, and (4) conversion concepts. Detailed descriptions of near term isolation concepts are provided. The descriptions include: (1) method of isolation, (2) waste forms that can be accommodated, (3) advantages and disadvantages, (4) facility and equipment requirements, (5) unusual operational or maintenance requirements, (6) information/technology development requirements, and (7) related investigations of the concept.
Date: April 1, 1980
Partner: UNT Libraries Government Documents Department

National Waste Terminal Storage Program Information Management Plan. Volume I. Management summary

Description: A comprehensive information management plan is needed for the processing of the large amount of documentation that will accumulate in the National Waste Terminal Storage program over the next decade. The plan will apply to all documentation from OWI contractors, subcontractors, and suppliers, and to external documentation from OWI organizations. (DLC)
Date: May 1, 1977
Partner: UNT Libraries Government Documents Department

National Waste Terminal Storage Program: planning and control plan. Volume II. Plan description

Description: Objective of the NWTS program planning and control plan is to provide the information necessary for timely and effective OWI management decisions. Purpose is to describe the concepts and techniques that will be utilized by OWI to establish structured, completely planned and controlled technical, cost, and schedule NWTS baselines from which performance or progress can be accurately measured.
Date: May 1, 1977
Partner: UNT Libraries Government Documents Department

National Waste Terminal Storage Program: critical element management concept. Volume II. Concept description

Description: The objective of the CEM Concept is to describe techniques for systematically identifying, evaluating, and influencing those technical, social, economic, political and institutional factors (i.e., events, trends and conditions) that are perceived as being probable uncertainties to the attainment of planned program objectives.
Date: May 1, 1977
Partner: UNT Libraries Government Documents Department

Analysis of transient history of underground excavations for radioactive waste isolation

Description: The constraints and phenomena which must be modeled in realizing a rational prediction of temperature history in a radioactive waste repository are presented. The effects of conductive and radiative heat transfer between the waste package and host rock are presented. Results of numerical investigations are utilized to present specific situations wherein analytical approximations to the waste canister geometry may be utilized. The paper also presents the results of approximations to the mean underground repository temperatures. The reliability of both methods of predicting temperatures is assessed through the comparison of predicted temperatures with measured temperatures from the Project Salt Vault field experiment. The design of experiments for model verification is discussed and a specific heater experiment which has been proposed is presented.
Date: August 1, 1977
Creator: Ratigan, J. & Van Sambeek, L.
Partner: UNT Libraries Government Documents Department

Analysis/plot generation code with significance levels computed using Kolmogorov-Smirnov statistics valid for both large and small samples

Description: This report describes a version of the TERPED/P computer code that is very useful for small data sets. A new algorithm for determining the Kolmogorov-Smirnov (KS) statistics is used to extend program applicability. The TERPED/P code facilitates the analysis of experimental data and assists the user in determining its probability distribution function. Graphical and numerical tests are performed interactively in accordance with the user's assumption of normally or log-normally distributed data. Statistical analysis options include computation of the chi-square statistic and the KS one-sample test statistic and the corresponding significance levels. Cumulative probability plots of the user's data are generated either via a local graphics terminal, a local line printer or character-oriented terminal, or a remote high-resolution graphics device such as the FR80 film plotter or the Calcomp paper plotter. Several useful computer methodologies suffer from limitations of their implementations of the KS nonparametric test. This test is one of the more powerful analysis tools for examining the validity of an assumption about the probability distribution of a set of data. KS algorithms are found in other analysis codes, including the Statistical Analysis Subroutine (SAS) package and earlier versions of TERPED. The inability of these algorithms to generate significance levels for sample sizes less than 50 has limited their usefulness. The release of the TERPED code described herein contains algorithms to allow computation of the KS statistic and significance level for data sets of, if the user wishes, as few as three points. Values computed for the KS statistic are within 3% of the correct value for all data set sizes.
Date: October 1, 1983
Creator: Kurtz, S.E. & Fields, D.E.
Partner: UNT Libraries Government Documents Department