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Record Nr. |
UNINA9910707689303321 |
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Autore |
Marshall William (William B. J.) |
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Titolo |
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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Pubbl/distr/stampa |
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Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , August 2016 |
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Descrizione fisica |
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1 online resource (xi, 99, A4 pages) : color illustrations |
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Soggetti |
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Boiling water reactors |
Spent reactor fuels - Storage |
Fuel burnup (Nuclear engineering) |
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Lingua di pubblicazione |
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Formato |
Materiale a stampa |
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Livello bibliografico |
Monografia |
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Note generali |
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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." |
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Nota di bibliografia |
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Includes bibliographical references (page 95-96). |
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