Neutronic analysis of the new Penn State Breazeale Reactor core design using MCNP5 code

D. Uçar, Kenan Unlu

Research output: Contribution to journalArticle

Original languageEnglish (US)
Pages (from-to)299-300
Number of pages2
JournalTransactions of the American Nuclear Society
Volume106
StatePublished - 2012

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Reactor cores

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality

Cite this

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title = "Neutronic analysis of the new Penn State Breazeale Reactor core design using MCNP5 code",
author = "D. U{\cc}ar and Kenan Unlu",
year = "2012",
language = "English (US)",
volume = "106",
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journal = "Transactions of the American Nuclear Society",
issn = "0003-018X",

}

Neutronic analysis of the new Penn State Breazeale Reactor core design using MCNP5 code. / Uçar, D.; Unlu, Kenan.

In: Transactions of the American Nuclear Society, Vol. 106, 2012, p. 299-300.

Research output: Contribution to journalArticle

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AU - Unlu, Kenan

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JF - Transactions of the American Nuclear Society

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