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Packaging design criteria for the MCO cask

Description: Approximately 2,100 metric tons of unprocessed, irradiated nuclear fuel elements are presently stored in the K Basins. To permit cleanup of the K Basins and fuel conditioning, the fuel will be transported from the K Basins to a Canister Storage Building in the 200 East Area. The purpose of this packaging design criteria is to provide criteria for the design, fabrication, and use of a packaging system to transport the large quantities of irradiated nuclear fuel elements positioned within Multipl… more
Date: January 1, 1996
Creator: Clements, M.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Spent Nuclear Fuel Project evaluation of multi-canister overpack venting and monitoring options during staging of K basins fuel

Description: This engineering study recommends whether multi-canister overpacks containing spent nuclear fuel from the Hanford K Basins should be staged in vented or a sealed, but ventable, condition during staging at the Canister Storage Building prior to hot vacuum conditioning and interim storage. The integrally related issues of MCO monitoring, end point criteria, and assessing the practicality of avoiding venting and Hot Vacuum Conditioning for a portion of the spent fuel are also considered.
Date: December 1, 1995
Creator: Wiborg, J.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Recent Progress on the Standardized DOE Spent Nuclear Fuel Canister

Description: The Department of Energy (DOE) has developed a set of containers for the handling, interim storage, transportation, and disposal in the national repository of DOE spent nuclear fuel (SNF). This container design, referred to as the standardized DOE SNF canister or standardized canister, was developed by the Department's National Spent Nuclear Fuel Storage Program (NSNFP) working in conjunction with the Office of Civilian Radioactive Waste Management (OCRWM) and the DOE spent fuel sites. This can… more
Date: August 1, 2002
Creator: Morton, Dana Keith; Snow, Spencer David; Rahl, Tommy Ervin; Hill, Thomas Johnathan & Morissette, R. P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Pressure Resistance Welding of High Temperature Metallic Materials

Description: Engineers from the Idaho National Laboratory (INL) have demonstrated an innovative method for seal or pinch welding stainless steel tubing. Sometimes a tube has fuel or contamination that must be contained, or the tube needs to be shortened or cut for handling, and the tube needs to have a guaranteed sealed weld that is both quick and easy. This technique was demonstrated in a laboratory using a resistance welding system with specially designed electrodes to ensure a tube end is seal welded or … more
Date: August 1, 2010
Creator: Zirker, Larry & Tyler, Craig
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Weld Tests Conducted by the Idaho National Laboratory

Description: During the fiscal year of 2006, the Idaho National Laboratory (INL) performed many tests and work relating to the Mobile Melt-Dilute (MMD) Project components. Tests performed on the Staubli quick disconnect fittings showed promising results, but more tests were needed validate the fittings. Changes were made to the shield plug design—reduced the closure groove weld depth between the top of the canister and the top plate of the shielding plug from 0.5-in to 0.375-in deep. Other changes include a… more
Date: February 1, 2007
Creator: Zirker, Larry; Lauerhass, Lance & Dowalo, James
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Testing and Analysis of Consolidated Sludge Samples from the 105 K East Basin Floor and Canisters

Description: The testing reported here was performed on K East Basin consolidated sludge samples to generate data needed for the evaluation and design of the systems that will be used to disposition the K Basin sludge to T-Plant for interim storage. The tests were conducted by Pacific Northwest National Laboratory from May through November 1999 under the direction of the Spent Nuclear Fuel (SNF) Project. The samples used in the work discussed here were collected by the SNF Characterization Project from the … more
Date: November 6, 2000
Creator: Bredt, Paul R. (BATTELLE (PACIFIC NW LAB)); Delegard, Calvin H. (BATTELLE (PACIFIC NW LAB)); Schmidt, Andrew J. (BATTELLE (PACIFIC NW LAB)) & Silvers, Kurt L. (BATTELLE (PACIFIC NW LAB))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Research on Spent Fuel Storage and Transportation in CRIEPI (Part 2 Concrete Cask Storage)

Description: Concrete cask storage has been implemented in the world. At a later stage of storage period, the containment of the canister may deteriorate due to stress corrosion cracking phenomena in a salty air environment. High resistant stainless steels against SCC have been tested as compared with normal stainless steel. Taking account of the limited time-length of environment with certain level of humidity and temperature range, the high resistant stainless steels will survive from SCC damage. In addit… more
Date: October 1, 2008
Creator: Shirai, Koji; Tani, Jyunichi; Arai, Taku; Watatu, Masumi; Takeda, Hirofumi; Saegusa, Toshiari et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Packaging Strategies for Criticality Safety for "Other" DOE Fuels in a Repository

Description: Since 1998, there has been an ongoing effort to gain acceptance of U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in the national repository. To accomplish this goal, the fuel matrix was used as a discriminating feature to segregate fuels into nine distinct groups. From each of those groups, a characteristic fuel was selected and analyzed for criticality safety based on a proposed packaging strategy. This report identifies and quantifies the important criticality parameters for … more
Date: June 1, 2004
Creator: Taylor, Larry L
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Multi Canister Overpack (MCO) Combustible Gas Management Leak Test Acceptance Criteria (OCRWM)

Description: The purpose of this document is to support the Spent Nuclear Fuel Project's combustible gas management strategy while avoiding the need to impose any requirements for oxygen free atmospheres within storage tubes that contain multi-canister overpacks (MCO). In order to avoid inerting requirements it is necessary to establish and confirm leak test acceptance criteria for mechanically sealed and weld sealed MCOs that are adequte to ensure that, in the unlikely event the leak test results for any M… more
Date: October 10, 2000
Creator: SHERRELL, D.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Compilation and Integration of K Basin Sludge Particle Size Analysis Data

Description: This report consolidates and integrates all of the particle size analysis data generated during the Hanford K Basin sludge characterization campaigns. The provides the most representative particle size distribution curves for the various K Basin sludge types. Understanding the particle size distribution of the sludge is necessary to design sludge retrieval and processing systems and to address sludge transportation and storage safety issues due to the potential reactivity of sludge.
Date: November 6, 2000
Creator: Bredt, Paul R.; Tingey, Joel M. & Schmidt, Andrew J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Criticality Analysis for Proposed Maximum Fuel Loading in a Standardized SNF Canister with Type 1a Baskets

Description: This document represents a summary version of the criticality analysis done to support loading SNF in a Type 1a basket/standard canister combination. Specifically, this engineering design file (EDF) captures the information pertinent to the intact condition of four fuel types with different fissile loads and their calculated reactivities. These fuels are then degraded into various configurations inside a canister without the presence of significant moderation. The important aspect of this study… more
Date: February 1, 2007
Creator: Pope, Chad; Taylor, Larry L. & Kim, Soon Sam
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analytical Results of DWPF Glass Sample Taken During Filling of Canister S01913

Description: The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 2 (SB2) in December 2001 as part of Sludge Receipt and Adjustment Tank (SRAT) Batch 208. Sludge Batch 2 consists of the contents of Tank 40 and Tank 8 in approximately equal proportions. The sludge slurry is received into the DWPF Chemical Processing Cell and is processed through the SRAT and Slurry Mix Evaporator Tank. The treated sludge slurry is then transferred to the Melter Feed Tank and fed to the melter. During th… more
Date: August 1, 2004
Creator: Cozzi, Alex D. & Bibler, N. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Retrieval Sub Project (FRS) Stuck Fuel Station Performance Test Data Report

Description: This document provides the test data report for Stuck Fuel Station Performance Testing in support of the Fuel Retrieval Sub-Project. The stuck fuel station was designed to provide a means of cutting open a canister barrel to release fuel elements, etc.
Date: February 23, 2000
Creator: Thielges, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Graphite Oxidation Thermodynamics/Reactions

Description: The vulnerability of graphite-matrix spent nuclear fuel to oxidation by the ambient atmosphere if the fuel canister is breached was evaluated. Thermochemical and kinetic data over the anticipated range of storage temperatures (200 to 400 C) were used to calculate the times required for a total carbon mass loss of 1 mgcm-2 from a fuel specimen. At 200 C, the time required to produce even this small loss is large, 900,000 yr. However, at 400 C the time required is only 1.9 yr. The rate of oxidati… more
Date: September 1, 1998
Creator: Propp, W.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Waste Form Compliance Plan for the Idaho National Engineering and Environmental Laboratory High-Level Waste

Description: The Department of Energy (DOE) has specific technical and documentation requirements for high-level waste (HLW) that is to be placed in a federal repository. This document describes in general terms the strategy to be used at the Idaho National Engineering and Environmental Laboratory (INEEL) to demonstrate that vitrified HLW, if produced at the INEEL, meets these requirements. Waste form, canister, quality assurance, and documentation specifications are discussed. Compliance strategy is given,… more
Date: May 1, 1999
Creator: Staples, B. A. & O'Holleran, T. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Canister Stress Corrosion Cracking Susceptibility Experimental Results

Description: The National Spent Nuclear Fuel Program is tasked with ensuring the U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) is acceptable for permanent disposal at a designated repository. From a repository acceptance criteria viewpoint and from a transportation viewpoint, of significant concern is the condition of the container at the time of shipment. Because the fuel will be in temporary storage for as much as 50 years, verification that no significant degradation has occurred to the … more
Date: March 1, 2003
Creator: Shelton-Davis, Colleen
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High Integrity Can Design Interfaces

Description: The National Spent Nuclear Fuel Program is chartered with facilitating the disposition of DOE-owned spent nuclear fuel to allow disposal at a geologic repository. This is done through coordination with the repository program and by assisting DOE Site owners of SNF with needed information, standardized requirements, packaging approaches, etc. The High Integrity Can (HIC) will be manufactured to provide a substitute or barrier enhancement for normal fuel geometry and cladding. The can would be ne… more
Date: August 1, 1998
Creator: Shaber, E.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Quick Look Report for Chemical Reactivity Modeling of Various Multi-Canister Overpack Breaches

Description: This report makes observations or shows trends in the response and does not specifically provide conclusions or predict the onset of bulk uranium oxidation safety margins based on hole size. Comprehensive analysis will be provided in the future. The report should animate discussions about the results and what should be analyzed further in the final analysis. This report intends only to show the response of the breached multi-canister overpack (MCO) as a function of event time using the GOTH_SNF… more
Date: April 1, 2002
Creator: Bratton, Robert Lawrence
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Spent Nuclear Fuel Project Technical Databook

Description: The Spent Nuclear Fuel (SNF) Project Technical Databook is developed for use as a common authoritative source of fuel behavior and material parameters in support of the Hanford SNF Project. The Technical Databook will be revised as necessary to add parameters as their Databook submittals become available.
Date: October 23, 1998
Creator: Reilly, M.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Recent Progress on the Standardized DOE Spent Nuclear Fuel Canister

Description: The Department of Energy (DOE) has developed a set of containers for the handling, interim storage, transportation, and disposal in the national repository of DOE spent nuclear fuel (SNF). This container design, referred to as the standardized DOE SNF canister or standardized canister, was developed by the Department's National Spent Nuclear Fuel Storage Program (NSNFP) working in conjunction with the Office of Civilian Radioactive Waste Management (OCRWM) and the DOE spent fuel sites. This can… more
Date: May 7, 2002
Creator: Morton, D.K.; Snow, S.D.; Rahl, T.E.; Hill, T.J. (INEEL) & Morissette, R.P. (Beckman and Associates, Inc.)
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Updated Volumetric Expansion Factors for K Basin Sludge During Storage

Description: Sludge has accumulated in the K East (KE) and K West (KW) Basins at the Hanford Site. This sludge contains metallic uranium and uranium oxides that will corrode, hydrate, and generate and consume gases during containerized storage. From these corrosion reactions, two sludge expansion mechanisms can be expected: 1) expansion of the volume of the sludge solids from the generation of corrosion oxidation products that occupy more space than the starting-state sludge; and 2) expansion of the bulk sl… more
Date: March 14, 2003
Creator: Schmidt, Andrew J. (BATTELLE (PACIFIC NW LAB)) & Delegard, Calvin H. (BATTELLE (PACIFIC NW LAB))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Analytical Evaluation of Preliminary Drop Tests Performed to Develop a Robust Design for the Standardized DOE Spent Nuclear Fuel Canister

Description: The Department of Energy (DOE) has developed a design concept for a set of standard canisters for the handling, interim storage, transportation, and disposal in the national repository, of DOE spent nuclear fuel (SNF). The standardized DOE SNF canister has to be capable of handling virtually all of the DOE SNF in a variety of potential storage and transportation systems. It must also be acceptable to the repository, based on current and anticipated future requirements. This expected usage manda… more
Date: August 1, 1999
Creator: Ware, A. G. (Jack); Morton, D. Keith; Smith, Nancy L.; Snow, Spencer D. & Rahl, Tom E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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