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Prompt neutron decay constants at delayed criticality for the Oak Ridge Research Reactor with 20 and 93 wt% 235U enriched fuel

โœ Scribed by G.E. Ragan; J.T. Mihalczo; R.C. Robinson

Book ID
103698007
Publisher
Elsevier Science
Year
1997
Tongue
English
Weight
675 KB
Volume
24
Category
Article
ISSN
0306-4549

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๐Ÿ“œ SIMILAR VOLUMES

97/01955 Prompt Neutron decay constants
97/01955 Prompt Neutron decay constants at delayed criticality for the oak ridge research reactor with 20 and 93 wt% 235U enriched fuel
๐Ÿ“‚ Article ๐Ÿ“… 1997 ๐Ÿ› Elsevier Science โš– 186 KB

97101952 Neutronic model for modal multichannel analysis of out-of-phase instability in boiling water reactor cores Hashimoto. K. ct al. Anrt. Nncl. &erg??, 1997, 24, (2) 99-l I I. This paper presents a neutronic model for linear multichannel analysis of out-of-phase (regional) instability in a BWR