학술논문

SACRD: a data base for fast reactor safety computer codes, contents and glossary of Version 1 of the system
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 SAFETY
MECHANICAL PROPERTIES
REACTOR ACCIDENTS
REACTOR MATERIALS
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
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. This document lists the contents of Version 1 and also serves as a glossary of terminology used in the data base. 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.