Abstract
The majority of safety computer codes used in the Liquid Metal Fast Breeder Reactor safety studies have been developed with funds provided by the Energy Research and Development Administration. Currently, the data used by these codes are collected by each user who must transcribe it for use in his study. This procedure, unfortunately, involves redundant effort and many times requires the user to ″evaluate″ physical property data, even though he has no expertise in this area. The Safety Analysis Computerized Reactor Data (SACRD) effort has been introduced in this paper to alleviate many of the difficulties cited above.
Original language | English |
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Pages | 1057-1065 |
Number of pages | 9 |
State | Published - 1976 |
Event | Accid Anal, Struct Dyn - Chicago, IL, USA Duration: Oct 5 1976 → Oct 8 1976 |
Conference
Conference | Accid Anal, Struct Dyn |
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City | Chicago, IL, USA |
Period | 10/5/76 → 10/8/76 |