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Analysis of NEPTUN bundle reflooding experiments using RELAP4/MOD6

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5564808
;
None
Research Organization:
EIR, Federal Institute for Reactor Research, 5303 Wurenlingen
OSTI ID:
5564808
Report Number(s):
CONF-830609-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 44
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ANALOG SYSTEMS
COMPUTER CODES
COMPUTERIZED SIMULATION
CORE FLOODING SYSTEMS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EXPERIMENTAL REACTORS
FUEL-COOLANT INTERACTIONS
FUNCTIONAL MODELS
H CODES
HEAT TRANSFER
LOSS OF COOLANT
M CODES
N CODES
R CODES
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTOR SIMULATORS
REACTORS
RESEARCH AND TEST REACTORS
ROD BUNDLES
SIMULATION
SIMULATORS