Thermal Neutron Scattering Data for the Moderator Materials H2O, D2O and ZrHx in ENDF-6 Format and as ACE Library for MCNP(X) Codes

Title

Author

M. Mattes and J. Keinert

Date

Apr 2005

DOI

Institute

International Atomic Energy Agency, Vienna, Austria

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16-Apr-2024

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