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].
- 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.
|General Note:|| Title from title screen (viewed on Sept. 8, 2016).
"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
Search for related items by subject
|Subject:||Boiling water reactors.
Spent reactor fuels > Storage.
Fuel burnup (Nuclear engineering)