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Analysis of prestressed concrete vessels for HCDA loads. [LMFBR]

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6525883
 [1];
  1. Argonne National Lab., IL
+ Show Author Affiliations
None
OSTI ID:
6525883
Report Number(s):
CONF-7811109-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 30
Country of Publication:
United States
Language:
English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
BUILDING MATERIALS
CONCRETES
CONTAINERS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
PRESTRESSED CONCRETE
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTOR VESSELS
REACTORS
SAFETY
STRESS ANALYSIS
STRESSES