Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire Scenario Metadata

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Title

  • Main Title Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire Scenario

Creator

  • Author: Adkins, Harold E.
    Creator Type: Personal
  • Author: Cuta, Judith M.
    Creator Type: Personal
  • Author: Koeppel, Brian J.
    Creator Type: Personal
  • Author: Guzman, Anthony D.
    Creator Type: Personal
  • Author: Bajwa, Christopher S.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization

Publisher

  • Name: Pacific Northwest National Laboratory (U.S.)
    Place of Publication: Richland, Washington
    Additional Info: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

Date

  • Creation: 2006-11-15

Language

  • English

Description

  • Content Description: On July 18, 2001, a freight train carrying hazardous (non-nuclear) materials derailed and caught fire while passing through the Howard Street railroad tunnel in downtown Baltimore, Maryland. The United States Nuclear Regulatory Commission (USNRC), one of the agencies responsible for ensuring the safe transportation of radioactive materials in the United States, undertook an investigation of the train derailment and fire to determine the possible regulatory implications of this particular event for the transportation of spent nuclear fuel by railroad. Shortly after the accident occurred, the USNRC met with the National Transportation Safety Board (NTSB, the U.S. agency responsible for determining the cause of transportation accidents), to discuss the details of the accident and the ensuing fire. Following these discussions, the USNRC assembled a team of experts from the National Institute of Standards and Technology (NIST), the Center for Nuclear Waste Regulatory Analyses (CNWRA), and Pacific Northwest National Laboratory (PNNL) to determine the thermal conditions that existed in the Howard Street tunnel fire and analyze the effects of this fire on various spent fuel transportation package designs. The Fire Dynamics Simulator (FDS) code, developed by NIST, was used to determine the thermal environment present in the Howard Street tunnel during the fire. The FDS results were used as boundary conditions in the COBRA-SFS and ANSYS® computer codes to evaluate the thermal performance of different package designs. The staff concluded that larger transportation packages resembling the HOLTEC Model No. HI STAR 100 and TransNuclear Model No. TN-68 would withstand a fire with thermal conditions similar to those that existed in the Baltimore tunnel fire event with only minor damage to peripheral components. This is due to their sizable thermal inertia and design specifications in compliance with currently imposed regulatory requirements. The staff also concluded that some components of smaller transportation packages resembling the NAC Model No. LWT, despite placement within an ISO container, could degrade. USNRC staff evaluated the radiological consequences of the package responses to the Baltimore tunnel fire. Though components in some packages heated up beyond their service temperatures, the staff determined that there would be no significant dose as a result of the fire for any of these and similar packages.
  • Physical Description: PDFN

Subject

  • Keyword: Spent Fuels Spent Fuel Transportation Packages, Baltimore Tunnel Fire
  • Keyword: Cargo
  • Keyword: Radioactive Wastes
  • Keyword: Specifications
  • Keyword: Compliance
  • Keyword: Radioactive Materials
  • Keyword: Spent Fuel Transportation Packages, Baltimore Tunnel Fire
  • Keyword: Boundary Conditions
  • STI Subject Categories: 11 Nuclear Fuel Cycle And Fuel Materials
  • Keyword: Simulators
  • Keyword: Nuclear Fuels
  • Keyword: Design
  • Keyword: Computer Codes
  • Keyword: Accidents
  • STI Subject Categories: 12 Management Of Radioactive Wastes, And Non-Radioactive Wastes From Nuclear Facilities
  • Keyword: Roads
  • Keyword: Performance
  • Keyword: Safety

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

  • Report No.: NUREG-CR-6886 Rev.1
  • Report No.: PNNL-15313
  • Grant Number: AC05-76RL01830
  • DOI: 10.2172/921269
  • Office of Scientific & Technical Information Report Number: 921269
  • Archival Resource Key: ark:/67531/metadc902643