Review of thorium-U233 cycle thermal reactor benchmark studies (AWBA Development Program) [electronic resource]

A survey is made of existing integral experiments for U233 systems and thorium-uranium based fuel systems. The aim is to understand to what extent they give a consistent test of ENDF/B-IV nuclear data. A principal result is that ENDF/B-IV leads to an underprediction of neutron leakage. Results from...

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Online Access: Online Access
Corporate Author: Bettis Atomic Power Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: West Mifflin, Pa. : Oak Ridge, Tenn. : Bettis Atomic Power Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1980.
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Call Number: E 1.99:wapd-tm-1456
E 1.99:wapd-tm-1456 Available