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Transient boiling calculations in rod bundles using the THEBES Code

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:7099754
;
None
Research Organization:
CEA CEN Cadarache-France, 13115 Saint Paul Les Durance
OSTI ID:
7099754
Report Number(s):
CONF-811103-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 39
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALKALI METALS
BOILING
BREEDER REACTORS
COMPUTER CODES
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FLUID FLOW
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
METALS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTORS
ROD BUNDLES
SODIUM
T CODES
TRANSIENTS
TWO-PHASE FLOW