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Domestic Resource of Uranium and Thorium : A Summary Based Upon Investigations by the u.s. Geological Survey

Description: From abstract: "This report summarizes our knowledge of the geology of radioactive raw materials and outlines the work done by the Geological Survey as well as that planned or recommended. An evaluation of uranium and thorium deposits is given in terms of known reserves and potential resources."
Date: April 1951
Creator: McKelvey, V. E.; Page, L. R.; Fischer, R. P. & Butler, A. P., Jr.
Partner: UNT Libraries Government Documents Department

Present Investigations of Radioactive Raw Materials by the Geological Survey and a Recommended Program for Future Work

Description: From abstract: "The Geological Survey's program of investigation of radioactive raw materials is presented herewith under present investigations, plans for future investigations, plan of operation, and cost of operation. This report was prepared at the request of the Atomic Energy Commission."
Date: April 1947
Creator: Butler, A. P., Jr. & Stead, F. W.
Partner: UNT Libraries Government Documents Department

Geologic Investigations of Radioactive Deposits Semiannual Progress Report

Description: This report is a statement of progress during a six-months period and gives the principal unclassified information developed in that period about investigations of radioactive materials in the United States and Alaska, and to a minor extent in foreign countries.
Date: June 1954
Creator: Geological Survey (U.S.)
Partner: UNT Libraries Government Documents Department

Selection of 3013 containers for field surveillance: LA-14310, Revision 1

Description: This document is the fifth in a series of reports that document the binning, statistical sampling, and sample selection of 3013 containers for field surveillance. 1,2,3,39 Revisions to binning assignments documented in this report are primarily a result of new prompt gamma data. This report also documents changes to the random sample specification resulting from these binning changes and identifies and provides the rationale for the engineering judgment sample items for Fiscal Year (FY) 2008 and 2009. This revision also updates the changes to the previous surveillance sample resulting from changes to the order that specific containers undergo surveillance. This report will continue to be reviewed regularly and revised as needed to meet the requirements of the surveillance program.
Date: April 1, 2009
Creator: Peppers, Larry; Kelly, Elizabeth; McClard, James; Friday, Gary; Venetz, Theodore & Stakebake, Jerry
Partner: UNT Libraries Government Documents Department

Radioactive Source Materials in Los Estados Unidos de Venezuela

Description: From Abstract: "This report summarizes data available on radioactive source materials in Los Estados Unidos de Venezuela accumulated by geologists of the Dirección Técnica de Geología and antecedent agencies prior to June 1951, and by the writers from June to November 1951."
Date: February 1953
Creator: Wyant, Donald G. & Sharp, William N.
Partner: UNT Libraries Government Documents Department

Development of nuclear analysis capabilities for DOE waste management activities. 1998 annual progress report

Description: 'The objective of this project is to develop and demonstrate prototypic analysis capabilities that can be used by the nuclear safety analysis practitioners to: (1) demonstrate a more thorough understanding of the underlying physics phenomena that can lead to improved reliability and defensibility of safety evaluations; and (2) optimize operations related to the handling, storage, transportation, and disposal of fissile material and DOE spent fuel. To address these problems, the project will investigate the implementation of sensitivity and uncertainty methods within existing Monte Carlo codes used for criticality safety analyses, as well as within a new deterministic code that allows specification of arbitrary grids to accurately model the geometry details required in a criticality safety analysis. This capability can facilitate improved estimations of the required subcritical margin and potentially enable the use of a broader range of experiments in the validation process. The new arbitrary-grid radiation transport code will also enable detailed geometric modeling valuable for improved accuracy in application to a myriad of other problems related to waste characterization. Application to these problems will also be explored. This report summarizes the progress achieved after only seven months of work on a three-year project.'
Date: June 1, 1998
Creator: Parks, C.V.; DeHart, M.D.; Broadhead, B.L. & Hopper, C.M.
Partner: UNT Libraries Government Documents Department

Modeling of diffusion of plutonium in other metals and of gaseous species in plutonium-based systems. 1998 annual progress report

Description: 'The problem being addressed is to establish standards for storage conditions for containers (e.g. stainless steel containers) meant to hold nuclear waste for long periods of time, e.g. fifty years, such as to ensure the integrity of the containers without being excessively conservative, i.e., being unnecessarily costly. Allowable storage temperature is an important parameter for the standards. Diffusion processes are central to certain processes that initiate corrosion of the containers or that lead to the release of gases increasing pressure that can rupture the container. The scientific goals of this project are: (1) to predict diffusion constants on an ab initio basis, i.e. diffusion distances in specified time at specified temperature, for atomic species from plutonium-based waste materials into storage container materials such as stainless steel or vice versa, (2) to predict the time development at specified temperature of complex diffusion processes in plutonium-based oxide type waste materials in the presence of water vapor such that gases may be released within a container. This predictive ability will help to provide information relevant to setting standards for waste container vessels and storage conditions. This project was initiated on September 15, 1997, so that this summary reports progress after about 2/3 of the first year of a three-year project.'
Date: June 1, 1998
Creator: Cooper, B.R. & Fernando, G.W.
Partner: UNT Libraries Government Documents Department

RadCat 3.0 user guide.

Description: RADTRAN is an internationally accepted program and code for calculating the risks of transporting radioactive materials. The first versions of the program, RADTRAN I and II, were developed for NUREG-0170 (USNRC, 1977), the first environmental statement on transportation of radioactive materials. RADTRAN and its associated software have undergone a number of improvements and advances consistent with improvements in both available data and computer technology. The version of RADTRAN currently bundled with RadCat is RADTRAN 6.0. This document provides a detailed discussion and a guide for the use of the RadCat 3.0 Graphical User Interface input file generator for the RADTRAN code. RadCat 3.0 integrates the newest analysis capabilities of RADTRAN 6.0 which includes an economic model, updated loss-of-lead shielding model, and unit conversion. As of this writing, the RADTRAN version in use is RADTRAN 6.0.
Date: May 1, 2009
Creator: Hinojosa, Daniel; Penisten, Janelle J.; Dennis, Matthew L.; Osborn, Douglas M.; Weiner, Ruth F.; Heames, Terence John et al.
Partner: UNT Libraries Government Documents Department

Definition and means of maintaining the ventilation system confinement portion of the PFP safety envelope

Description: The Plutonium Finishing Plant Heating Ventilation and Cooling system provides for the confinement of radioactive releases to the environment and provides for the confinement of radioactive contamination within designated zones inside the facility. This document identifies the components and procedures necessary to ensure the HVAC system provides these functions. Appendices E through J provide a snapshot of non-safety class HVAC equipment and need not be updated when the remainder of the document and Appendices A through D are updated.
Date: March 5, 1997
Creator: Dick, J.D.; Grover, G.A. & O`Brien, P.M., Fluor Daniel Hanford
Partner: UNT Libraries Government Documents Department

Test and evaluation report for Westinghouse Hanford Company`s 1-L liquid shipper, docket 95-41-7A, Type A container

Description: This report incorporates the U.S. Department of Energy, Office of Facility Safety Analysis (DOE/EH-32) approval letter for packaging use. This report documents the U.S. Department of Transportation Specification 7A Type A (DOT-7A) compliance test results of the 1-L Liquid Shipper packaging. The approved packaging system is designed to ship Type A quantities of radioactive materials, normal form. Contents may be liquid or solid form. Liquid contents must have a specific gravity {lt}2. Solid materials are limited in weight, to include packaging, to the gross weight of the as-tested liquids and bottles.
Date: March 13, 1996
Creator: Kelly, D.L.
Partner: UNT Libraries Government Documents Department

Test and evaluation report for Lockheed Idaho Technologies Company, arrow-pak packaging, docket 95-40-7A, type A container

Description: This report incorporates the U.S. Department of Energy, Office of Facility Safety Analysis (DOE/EH-32) approval letter for packaging use. This report documents the U.S. Department of Transportation Specification 7A Type A (DOT-7A) compliance test results of the Arrow-Pak packaging. The Arrow-Pak packaging system consists of Marlex M-8000 Driscopipe, manufactured by Phillips-Driscopipe, Inc., and is sealed with two dome-shaped end caps manufactured from the same materials. The patented sealing process involves the use of electrical energy to heat opposing faces of the pipe and end caps, and hydraulic rams to press the heated surfaces together. This fusion process produces a homogeneous bonding of the end cap to the pipe. The packaging may be used with or without the two internal plywood spacers. This packaging configuration described in this report is designed to ship Type A quantities of solid radioactive materials.
Date: March 14, 1996
Creator: Kelly, D.L.
Partner: UNT Libraries Government Documents Department

Statement of work for analytical services provided to Westinghouse Hanford Company by the Pacific Northwest National Laboratory analytical chemistry laboratory

Description: The purpose of this Statement of Work is to establish laboratory analytical criteria and requirements associated with radioactive airborne emissions measurements. The criteria and requirements in this document apply to airborne emissions measurement activities funded by WHC managed facilities in the 300 and 400 areas.
Date: May 24, 1996
Creator: Perry, J. K.
Partner: UNT Libraries Government Documents Department

Introduction to naturally occurring radioactive material

Description: Naturally occurring radioactive material (NORM) is everywhere; we are exposed to it every day. It is found in our bodies, the food we eat, the places where we live and work, and in products we use. We are also bathed in a sea of natural radiation coming from the sun and deep space. Living systems have adapted to these levels of radiation and radioactivity. But some industrial practices involving natural resources concentrate these radionuclides to a degree that they may pose risk to humans and the environment if they are not controlled. Other activities, such as flying at high altitudes, expose us to elevated levels of NORM. This session will concentrate on diffuse sources of technologically-enhanced (TE) NORM, which are generally large-volume, low-activity waste streams produced by industries such as mineral mining, ore benefication, production of phosphate Fertilizers, water treatment and purification, and oil and gas production. The majority of radionuclides in TENORM are found in the uranium and thorium decay chains. Radium and its subsequent decay products (radon) are the principal radionuclides used in characterizing the redistribution of TENORM in the environment by human activity. We will briefly review other radionuclides occurring in nature (potassium and rubidium) that contribute primarily to background doses. TENORM is found in many waste streams; for example, scrap metal, sludges, slags, fluids, and is being discovered in industries traditionally not thought of as affected by radionuclide contamination. Not only the forms and volumes, but the levels of radioactivity in TENORM vary. Current discussions about the validity of the linear no dose threshold theory are central to the TENORM issue. TENORM is not regulated by the Atomic Energy Act or other Federal regulations. Control and regulation of TENORM is not consistent from industry to industry nor from state to state. Proposed regulations are moving from ...
Date: August 1, 1997
Creator: Egidi, P.
Partner: UNT Libraries Government Documents Department

Determination of Fire Enviroment in Stacked Cargo Containers with Radioactive Materials Packages

Description: Results from a Fire Test with a three-by-three stack of standard 6 m long International Standards Organization shipping containers containing combustible fuels and empty radioactive materials packages are reported and discussed. The stack is intended to simulate fire conditions that could occur during on-deck stowage on container cargo ships. The fire is initated by locating the container stack adjacent to a 9.8 x 6 m pool fire. Temperatures of both cargoes (empty and simulated radioactive materials packages) and containers are recorded and reported. Observations on the duration, intensity and spread of the fire are discussed. Based on the results, models for simulation of fire exposure of radioactive materials packages in such fires are suggested.
Date: May 1, 1999
Creator: Arviso, M.; Bobbe, J.G.; Dukart, R.D. & Koski, J.A.
Partner: UNT Libraries Government Documents Department