CENTRAL COMPUTERIZED DATA BASE FOR LIQUID METAL FAST BREEDER REACTOR SAFETY CODES.

H. Alter, G. F. Flanagan, N. M. Greene

Research output: Contribution to conferencePaperpeer-review

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 languageEnglish
Pages1057-1065
Number of pages9
StatePublished - 1976
EventAccid Anal, Struct Dyn - Chicago, IL, USA
Duration: Oct 5 1976Oct 8 1976

Conference

ConferenceAccid Anal, Struct Dyn
CityChicago, IL, USA
Period10/5/7610/8/76

Fingerprint

Dive into the research topics of 'CENTRAL COMPUTERIZED DATA BASE FOR LIQUID METAL FAST BREEDER REACTOR SAFETY CODES.'. Together they form a unique fingerprint.

Cite this