학술논문

SACRD: a data base for fast reactor safety computer codes, general description
Document Type
Technical Report
Author
Source
Subject
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS COMPUTER CODES
S CODES
LMFBR TYPE REACTORS
REACTOR ACCIDENTS
MATHEMATICAL MODELS
DATA COMPILATION
REACTOR SAFETY
ACCIDENTS
BREEDER REACTORS
DATA
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
INFORMATION
LIQUID METAL COOLED REACTORS
NUMERICAL DATA
REACTORS
SAFETY 220900* -- Nuclear Reactor Technology-- Reactor Safety
210500 -- Power Reactors, Breeding
Language
English
Abstract
SACRD is a data base of material properties and other handbook data needed in computer codes used for fast reactor safety studies. Data are available in the thermodynamics, heat transfer, fluid mechanics, structural mechanics, aerosol transport, meteorology, neutronics, and dosimetry areas. Tabular, graphical and parameterized data are provided in many cases. A general description of the SACRD system is presented in the report.