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Criticality-Control Applications in the Nuclear Industry for Thermal Spray Amorphous Metal and Ceramic Coatings

Description: Amorphous metal and ceramic thermal spray coatings have been developed that can be used to enhance the corrosion resistance of containers for the transportation, aging and disposal of spent nuclear fuel and high-level radioactive wastes. Iron-based amorphous metal formulations with chromium, molybdenum and tungsten have shown the corrosion resistance believed to be necessary for such applications. Rare earth additions enable very low critical cooling rates to be achieved. The boron content of t… more
Date: July 18, 2007
Creator: Farmer, J & Choi, J
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Applications in the Nuclear Industry for Corrosion-Resistant Amorphous-Metal Thermal-Spray Coatings

Description: Amorphous metal and ceramic thermal spray coatings have been developed that can be used to enhance the corrosion resistance of containers for the transportation, aging and disposal of spent nuclear fuel and high-level radioactive wastes. Fe-based amorphous metal formulations with chromium, molybdenum and tungsten have shown the corrosion resistance believed to be necessary for such applications. Rare earth additions enable very low critical cooling rates to be achieved. The boron content of the… more
Date: July 18, 2007
Creator: Farmer, J & Choi, J
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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General purpose heat source task group. Final report

Description: The results of thermal analyses and impact tests on a modified design of a /sup 238/Pu-fueled general purpose heat source (GPHS) for spacecraft power supplies are presented. This work was performed to establish the safety of a heat source with pyrolytic graphite insulator shells located either inside or outside the graphite impact shell. This safety is dependent on the degree of aerodynamic heating of the heat source during reentry and on the ability of the heat source capsule to withstand impa… more
Date: September 18, 1979
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Computer modeling of nuclear waste storage canister corrosion

Description: Current plans for nuclear waste disposal include placing the waste in a canister to isolate it from the repository environment for 1000 years. Corrosion prediction techniques are currently inadequate to quarantee the canister performance over this length of time. We are attempting to better predict the corrosion process with the help of computer modeling. We developed a program to calculate anodic and cathodic polarization curves using Tafel slopes, equilibrium exchange current densities, and o… more
Date: October 18, 1979
Creator: Cottrell, P.T.; Ludemann, W.D. & McCright, R.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Safety Analysis Report for Packaging: The unirradiated fuel shipping container USA/9853/AF

Description: The HFBR Unirradiated Fuel Shipping Container was designed and fabricated at the Oak Ridge National Laboratory in 1978 for the transport of fuel for the High Flux Beam Reactor (HFBR) for Brookhaven National Laboratory. The package has been evaluated analytically, as well as the comparison to tests on similar packages, to demonstrate compliance with the applicable regulations governing packages in which radioactive and fissile materials are transported. The contents of this Safety Analysis Repor… more
Date: October 18, 1991
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Basic data report: Canister penetration system with relative humidity and pressure sensors

Description: This work originates from a task assignment. This basic data report is for design and fabrication of a canister penetration system for use in these experiments. The basic system was designed and fabricated as a result of a previous task assignment and three associated task plans. The new system, which will be used on canistered waste forms produced during the DWPF Start up Test Program, will be a modification of the previous systems. Hence the seven items identified in the next paragraph have b… more
Date: March 18, 1992
Creator: Harbour, J.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HEDL contribution to Office of Nuclear Waste Isolation. May monthly report

Description: Progress is reported in the following areas of study: spent fuel characterization equipment; spent fuel characterization; and spent fuel/package performance. Some of the highlights are: calorimetry of Turkey Point Assembly D04 subsequently emplaced in the Climax-Spent Fuel Test (C-SFT) was completed; all data from the destructive examination of five fuel rods pulled from the C-SFT assemblies are being reduced and analyzed to provide a description of the pre-test condition for the C-SFT; work is… more
Date: June 18, 1980
Creator: Cantley, D. A. & Knecht, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SLUDGE TREATMENT PROJECT ENGINEERED CONTAINER RETRIEVAL AND TRANSFER SYSTEM PRELIMINARY DESIGN HAZARD ANALYSIS SUPPLEMENT 1

Description: This 'What/If' Hazards Analysis addresses hazards affecting the Sludge Treatment Project Engineered Container Retrieval and Transfer System (ECRTS) NPH and external events at the preliminary design stage. In addition, the hazards of the operation sequence steps for the mechanical handling operations in preparation of Sludge Transport and Storage Container (STSC), disconnect STSC and prepare STSC and Sludge Transport System (STS) for shipping are addressed.
Date: July 18, 2011
Creator: GR, FRANZ & RH, MEICHLE
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ACCEPTABILITY ENVELOPE FOR METAL HYDRIDE-BASED HYDROGEN STORAGE SYSTEMS

Description: The design and evaluation of media based hydrogen storage systems requires the use of detailed numerical models and experimental studies, with significant amount of time and monetary investment. Thus a scoping tool, referred to as the Acceptability Envelope, was developed to screen preliminary candidate media and storage vessel designs, identifying the range of chemical, physical and geometrical parameters for the coupled media and storage vessel system that allow it to meet performance targets… more
Date: July 18, 2011
Creator: Hardy, B.; Corgnale, C.; Tamburello, D.; Garrison, S. & Anton, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Computer simulations of high pressure systems

Description: Numerical methods are capable of solving very difficult problems in solid mechanics and gas dynamics. In the design of engineering structures, critical decisions are possible if the behavior of materials is correctly described in the calculation. Problems of current interest require accurate analysis of stress-strain fields that range from very small elastic displacement to very large plastic deformation. A finite difference program is described that solves problems over this range and in two a… more
Date: July 18, 1977
Creator: Wilkins, M. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

EXAMINATION OF SHIPPING PACKAGES 9975-01818, 9975-01903 AND 9975-02287

Description: Three 9975 shipping packages were examined to investigate the non-conforming condition of an axial air gap greater than 1 inch. This condition typically indicates the presence of excess moisture in the fiberboard overpack, and may be accompanied by degradation in the fiberboard properties. The package with the largest axial air gap (9975-01818, with an air gap of 1.437 inches) was found to contain significant excess moisture, and the lower fiberboard assembly was covered with mold and was signi… more
Date: November 18, 2009
Creator: Daugherty, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DEVELOPMENT AND TESTING OF THE BLANTON CLAMSHELL CLOSUREFOR USE ON RADIOACTIVE MATERIAL PACKAGING DRUMS

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 exte… more
Date: October 18, 2007
Creator: Blanton, P
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual

Description: The mission of the Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying Facility (CVDF) is to achieve the earliest possible removal of free water from Multi-Canister Overpacks (MCOs). The MCOs contain metallic uranium SNF that have been removed from the 100K Area fuel storage water basins (i.e., the K East and K West Basins) at the US. Department of Energy Hanford Site in Southeastern Washington state. Removal of free water is necessary to halt water-induced corrosion of exposed uranium surfaces… more
Date: November 18, 2000
Creator: Irwin, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THERMAL EVALUATION OF THE CONCEPTUAL DHLW DISPOSAL CONTAINER

Description: This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) as specified in the Waste Package Implementation Plan and Waste Package Plan. The design data request addressed herein is: (1) Characterize the conceptual design high-level waste (DHLW) disposal container design to show that the design is feasible for use in the MGDS environment when loaded with a borosilicate glass waste form which is based upon the reference 5.12 and 5.14 glass w… more
Date: December 18, 1995
Creator: Lotz, T.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CORROSION RELIABILITY PREDICTION: LONG TERM NUCLEAR WASTE STORAGE IN YUCCA MOUNTAIN

Description: The US. Department of Energy has proposed the disposal of high level nuclear waste from commercial and defense reactors in a mined geologic repository under Yucca Mountain, Nevada. The waste will be stored in metallic canisters. The barrier against corrosion will be an Alloy 22 canister and a Ti Grade 7 drip shield. Both of these materials are extremely corrosion resistant. The environment inside Yucca Mountain is relatively benign, but the long time period over which these materials must resis… more
Date: August 18, 2005
Creator: Frankel, G.S.; Tada, E. & Maier, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Low-cost flexible packaging for high-power Li-Ion HEV batteries.

Description: Batteries with various types of chemistries are typically sold in rigid hermetically sealed containers that, at the simplest level, must contain the electrolyte while keeping out the exterior atmosphere. However, such rigid containers can have limitations in packaging situations where the form of the battery is important, such as in hand-held electronics like personal digital assistants (PDAs), laptops, and cell phones. Other limitations exist as well. At least one of the electrode leads must b… more
Date: June 18, 2004
Creator: Jansen, A. N.; Amine, K. & Henriksen, G. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CH Packaging Operations for High Wattage Waste at LANL

Description: This procedure provides instructions for assembling the following contact-handled (CH) packaging payloads: - Drum payload assembly - Standard Waste Box (SWB) assembly - Ten-Drum Overpack (TDOP) In addition, this procedure also provides operating instructions for the TRUPACT-II CH waste packaging. This document also provides instructions for performing ICV and OCV preshipment leakage rate tests on the following packaging seals, using a nondestructive helium (He) leak test: - ICV upper main O-rin… more
Date: December 18, 2002
Creator: Westinghouse TRU Solutions LLC
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Design Report Shippingport Spent Fuel Drying and Inerting System

Description: A process description and system flow sheets have been prepared to support the design/build package for the Shippingport Spent Fuel Canister drying and inerting process skid. A process flow diagram was prepared to show the general steps to dry and inert the Shippingport fuel loaded into SSFCs for transport and dry storage. Flow sheets have been prepared to show the flows and conditions for the various steps of the drying and inerting process. Calculations and data supporting the development of … more
Date: May 18, 2000
Creator: Jeppson, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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COMMERCIAL SNF ACCIDENT RELEASE FRACTIONS

Description: The purpose of this design analysis is to specify and document the total and respirable fractions for radioactive materials that are released from an accident event at the Monitored Geologic Repository (MGR) involving commercial spent nuclear fuel (CSNF) in a dry environment. The total and respirable release fractions will be used to support the preclosure licensing basis for the MGR. The total release fraction is defined as the fraction of total CSNF assembly inventory, typically expressed as … more
Date: October 18, 1999
Creator: Bader, S.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Canister Storage Building Compliance Assessment SNF Project NRC Equivalency Criteria - HNF-SD-SNF-DB-003

Description: This document presents the Project's position on compliance with the SNF Project NRC Equivalency Criteria - HNF-SD-SNF-DB-003, Spent Nuclear Fuel Project Path Forward Additional NRC Requirements. No non-compliances are shown. The compliance statements have been reviewed and approved by DOE. Open items are scheduled to be closed prior to project completion.
Date: May 18, 2000
Creator: Black, D. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design of a 20-kWp photovoltaic concentrator experiment at Fauquier High School, Warrenton, Virginia

Description: Solar Corporation designed a photovoltaic concentrator system for Fauquier High School in Warrenton, Virginia, 40 miles west of Washington, DC. The system provides both electrical energy from the photovoltaic modules and thermal energy from the cooling of those modules. Direct current electrical energy from the photovoltaic modules will be first converted to ac and then used to provide power for lighting in the vocational/technical building and the system control building. Instead of being reje… more
Date: October 18, 1979
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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