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Axial moderator density distributions, control blade usage, and axial burnup distributions for extended BWR burnup credit / prepared by William (B.J.) Marshall [and three others].

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Record details

  • Physical Description: 1 online resource (xi, 99 pages, A4 pages) : color illustrations
  • Publisher: Washington, DC : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, August 2016.

Content descriptions

General Note: Title from title screen (viewed on Sept. 8, 2016).
"NUREG/CR-7224."
"ORNL/TM-2015/544."
"Manuscript completed: April 2016; date published: August 2016."
"Oak Ridge National Laboratory."
"Mourad Aissa, NRC project manager."
Bibliography, etc. Note: Includes bibliographical references (page 95-96).
Type of Report and Period Covered Note: Technical.
Funding Information Note: Sponsored by the Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission NRC JCN V6452
Subject: Boiling water reactors.
Spent reactor fuels > Storage.
Fuel burnup (Nuclear engineering)

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