Stress analysis of the LOFT core barrel for LOCA + SSE loads

Technical Report · Fri Jul 07 00:00:00 EDT 1978

DOI:https://doi.org/10.2172/6872039· OSTI ID:6872039

Blandford, R. K.

The results of a dynamic analysis of the LOFT Reactor Core Barrel for faulted conditions are presented in this report. Loading conditions considered were seismic accelerations resulting from a Safe Shutdown Earthquake (SSE) and pressure loadings from both a hot leg and a cold leg Loss-of-Coolant Accident (LOCA) break. Maximum stresses in the core barrel, resulting from these conditions, are presented with comparisons to Code allowables. Stresses were found to be within allowables for the faulted condition as defined in the ASME Code (1977), Appendix F.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6872039
• Report Number(s): LTR-1115-44; RE-A-78-117; TRN: 79-001149
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOFT REACTOR
REACTOR INTERNALS
EARTHQUAKES
LOSS OF COOLANT
SEISMIC EFFECTS
STRESS ANALYSIS
ACCIDENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SEISMIC EVENTS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors