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Reactor core transient analysis using coupled neutronics and thermal-hydraulic models

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6870751
;
None
Research Organization:
KWU-Germany, D-8520 Erlangen
OSTI ID:
6870751
Report Number(s):
CONF-790519-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 31
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
COMPUTER CODES
CONTROL ELEMENTS
EVALUATION
I CODES
MATHEMATICAL MODELS
REACTOR COMPONENTS
REACTOR CORES
SCRAM RODS
STEAM LINES
THERMODYNAMICS
TRANSIENTS