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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

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


Description: This paper describes the sealing performance testing and results of silver-plated inconel Spring Energized C-Rings used for tritium containment in radioactive shipping packagings. The test methodology used follows requirements of the American Society of Mechanical Engineers (ASME) summarized in ASME Pressure Vessel Code (B&PVC), Section V, Article 10, Appendix IX (Helium Mass Spectrometer Test - Hood Technique) and recommendations by the American National Standards Institute (ANSI) described in ANSI N14.5-1997. The tests parameters bound the predicted structural and thermal responses from conditions defined in the Code of Federal Regulations 10 CFR 71. The testing includes an evaluation of the effects of pressure, temperature, flange deflection, surface roughness, permeation, closure torque, torque sequencing and re-use on performance of metal C-Ring seals.
Date: October 23, 2007
Creator: Blanton, P & Kurt Eberl, K
Partner: UNT Libraries Government Documents Department


Description: This report details redesign of a commercially available rotary microfilter to meet the operational and maintenance requirements for radioactive service. Personnel developed the design and coordinated procurement of two filters followed by testing of one unit. System testing examined the ability to rinse soluble material from the system, filtration performance using several insoluble solids loadings, effectiveness in washing sludge, amount of wear to parts and maintenance of the system including the insertion and removal of the filter stack, and the ability to flush solids from the system. The test program examined flushing the filter for soluble material by filling the system with a Rhodamine WT dye solution. Results showed that draining the system and rinsing with 50 gallons of water resulted in grater than 100X reduction of the dye concentration. Personnel determined filter performance using various amounts of insoluble sludge solids ranging from 0.06 to 15 weight percent (wt%) insoluble solids in a 3 molar (M) sodium simulated supernate. Through approximately 120 hours of start-and-stop (i.e., day shift) operation and various insoluble solids loadings, the filter produced filtration rates between 3 and 7 gallons per minute (gpm) (0.12-0.29 gpm/ft{sup 2}) for a 25-disk filter. Personnel washed approximately 80 gallons of simulated sludge using 207 gallons of inhibited water. Washing occurred at constant volume with wash water fed to a well mixed tank at the same rate as filtrate removal. Performance measurement involved collecting and analyzing samples throughout the washing for density and sodium content. Results showed an effective washing, mimicking a predicted dilution calculation for a well mixed tank and reducing the sodium concentration from 3.2 M to less than 0.3 M. Filtration rates during the washing process ranged between 3 and 4.3 gpm for one filter unit. The filter system then concentrated the washed 15 wt% insoluble solids slurry ...
Date: September 29, 2006
Creator: Herman, D; Michael Poirier, M & Samuel Fink, S
Partner: UNT Libraries Government Documents Department

Shipment of Small Quantities of Unspecified Radioactive Material in Chalfant Packagings

Description: In the post 6M era, radioactive materials package users are faced with the disciplined operations associated with use of Certified Type B packagings. Many DOE, commercial and academic programs have a requirement to ship and/or store small masses of poorly characterized or unspecified radioactive material. For quantities which are small enough to be fissile exempt and have low radiation levels, the materials could be transported in a package which provides the required containment level. Because their Chalfant type containment vessels meet the highest standard of containment (helium leak-tight), the 9975, 9977, and 9978 are capable of transporting any of these contents. The issues associated with certification of a high-integrity, general purpose package for shipping small quantities of unspecified radioactive material are discussed and certification of the packages for this mission is recommended.
Date: June 12, 2009
Creator: Smith, Allen; Abramczyk, Glenn; Nathan, Steven & Bellamy, Steve
Partner: UNT Libraries Government Documents Department


Description: This paper provides a brief history of the U.S. Type B 6M specification container, its introduction into U.S. Code of federal regulations and its scheduled elimination three decades later. The paper also presents development, testing and deployment by the Department of Energy (DOE) of an enhanced drum closure called the 'Blanton Clamshell' (patent pending) that was designed to replace the standard open-head C-ring closure for the 55- and 85-gallon drums described in the 6M specification to extend their safe use. Nuclear Filter Technology has the Exclusive License for Clamshell production. Drum packages utilizing the standard C-ring closure have been a main-stay for over a half of a century in the national and international nuclear industry for shipping radioactive materials and will remain so in the foreseeable future. Drum package use in the U.S. increased heavily in the 1950's with development of the Weapons Complex and subsequently the commercial nuclear reactor industry.
Date: October 18, 2007
Creator: Blanton, P
Partner: UNT Libraries Government Documents Department


Description: The Model 9975 Shipping Package is the latest in a series (9965, 9968, etc.) of radioactive material shipping packages that have been the mainstay for shipping radioactive materials for several years. The double containment vessels are relatively simple designs using pipe and pipe cap in conjunction with the Chalfont closure to provide a leak-tight vessel. The fabrication appears simple in nature, but the history of fabrication tells us there are pitfalls in the different fabrication methods and sequences. This paper will review the problems that have arisen during fabrication and precautions that should be taken to meet specifications and tolerances. The problems and precautions can also be applied to the Models 9977 and 9978 Shipping Packages.
Date: May 7, 2008
Creator: May, C & Allen Smith, A
Partner: UNT Libraries Government Documents Department


Description: During normal operations at the Department of Energy's Hanford Site in Hanford, WA, drugstore beetles were found within the fiberboard subassemblies of two 9975 Shipping Packages. The Department of Energy's Packaging Certification Program (EM-60) directed a thorough investigation to determine if the drugstore beetles were causing damage that would be detrimental to the safety performance of the Celotex. The Savannah River National Laboratory is continuing to conduct the investigation with entomological expertise being provided by Clemson University. The outcome from the investigation conducted over the previous year was that no discernible damage had been caused by the drugstore beetles. One of the two packages has been essentially untouched over the past year and has only been opened to visually inspect for additional damage. This paper will provide details and results of the ongoing investigation of that package.
Date: June 8, 2009
Creator: Loftin, B.
Partner: UNT Libraries Government Documents Department

Spectrophotometric and Calorimetric Studies of Np(V) Complexation with Sulfate at 10-70oC

Description: Sulfate, one of the inorganic constituents in the groundwater of nuclear waste repository, could affect the migration of radioactive materials by forming complexes. Spectrophotometric and microcalorimetric titrations were performed to identify the Np(V)/sulfate complex and determine the equilibrium constants and enthalpy of complexation at 10-70 C. Results show that the complexation of Np(V) with sulfate is weak but slightly enhanced by the increase in temperature. The complexation is endothermic and becomes more endothermic with the increase in temperature. The enhanced complexation at elevated temperatures is due to the increasingly larger entropy of complexation that exceeds the increase in enthalpy, suggesting that the complexation of Np(V) with sulfate is entropy-driven.
Date: June 16, 2008
Creator: Rao, Linfeng; Tian, Guoxin; Xia, Yuanxian & Friese, Judah I.
Partner: UNT Libraries Government Documents Department


Description: The Department of Energy, Richland Operations (DOE-RL) recently restructured its Hanford work scope, awarding two new contracts over the past several months for a total of three contracts to manage the sites cleanup efforts. DOE-RL met with key contractor personnel prior to and during contract transition to ensure site welding activities had appropriate oversight and maintained code compliance. The transition also provided an opportunity to establish a single site-wide function that would provide welding and materials engineering services to the Hanford site contractors: CH2M HILL Plateau Remediation Company (CHPRC); Mission Support Alliance (MSA); Washington River Protection Solutions (WRPS); and Washington Closure Hanford (WCH). Over the years, multiple and separate welding programs (amongst the several contractors) existed at the Hanford site leading to inefficiencies resulting from duplication of administrative efforts, maintenance of welding procedures, welder performance certifications, etc. The new, single program eliminates these inefficiencies. The new program, co-managed by two of the sites' new contractors, the CHPRC ('owner' of the program and responsible for construction welding services) and the MSA (provides maintenance welding services), provides more than just the traditional construction and maintenance welding services. Also provided, are welding engineering, specialty welding development/qualification for the closure of radioactive materials containers and materials evaluation/failure analysis. The following describes the new Hanford site welding program.
Date: November 19, 2009
Creator: Cannell, G. R.
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

A needs assessment for DOE`s packaging and transportation activities - a look into the twenty-first century

Description: The U.S. Department of Energy (DOE) has performed a department-wide scoping of its packaging and transportation needs and has arrived at a projection of these needs for well into the twenty-first century. The assessment, known as the Transportation Needs Assessment (TNA) was initiated during August 1994 and completed in December 1994. The TNA will allow DOE to better prepare for changes in its transportation requirements in the future. The TNA focused on projected, quantified shipping needs based on forecasts of inventories of materials which will ultimately require transport by the DOE for storage, treatment and/or disposal. In addition, experts provided input on the growing needs throughout DOE resulting from changes in regulations, in DOE`s mission, and in the sociopolitical structure of the United States. Through the assessment, DOE`s transportation needs have been identified for a time period extending from the present through the first three decades of the twenty-first century. The needs assessment was accomplished in three phases: (1) defining current packaging, shipping, resource utilization, and methods of managing packaging and transportation activities; (2) establishing the inventory of materials which DOE will need to transport on into the next century and scenarios which project when, from where, and to where these materials will need to be transported; and (3) developing requirements and projected changes for DOE to accomplish the necessary transport safely and economically.
Date: December 31, 1995
Creator: Pope, R.; Turi, G.; Brancato, R.; Blalock, L. & Merrill, O.
Partner: UNT Libraries Government Documents Department