On the equivalence of neutron source and flux spectra
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- 作者：Ga&scaron ; per Žerovnik ; gasper.zerovnik@ijs.si" class="auth_mail" title="E-mail the corresponding author ; Jure Beričič jure.bericic@ijs.si" class="auth_mail" title="E-mail the corresponding author ; Luka Snoj luka.snoj@ijs.si" class="auth_mail" title="E-mail the corresponding author
- 关键词：Neutron density ; Neutron flux ; Neutron source ; Neutron transport ; Monte Carlo codes ; MCNP ; 252Cf fission spectrum
- 刊名：Annals of Nuclear Energy
- 出版年：2017
- 出版时间：January 2017
- 年：2017
- 卷：99
- 期：Complete
- 页码：54-57
- 全文大小：472 K
文摘
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Neutron source spectrum is under certain conditions proportional to the flux spectrum.
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The source/flux equivalence is met in optically (for neutrons) thin volume.
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Neutron source/flux equivalence has implications in simplification of computational models.