Stress analysis of LOFT Emergency Core Coolant System modification (left and right side)

Technical Report · Thu Aug 31 04:00:00 EDT 1978

DOI:https://doi.org/10.2172/6471667· OSTI ID:6471667

Kido, C.

A stress analysis has been performed on proposed modifications to the Emergency Core Coolant System right and left side. For the right side thermal expansion and seismic loads were considered. Results of a previous report using dead weight, design LOCE, and LOCA loads were treated as valid and not repeated here. For the left side LOCE loading only was considered. The results of a previous analysis using dead weight, thermal, and LOCE loads were treated as valid and again not repeated here. Review of the analysis indicated that both proposed modifications pass the requirements of the ASME Boiler and Pressure Vessel Code Section III for Class 1 and 2 piping.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 6471667
• Report Number(s): LTR-113-40
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ECCS
ENGINEERED SAFETY SYSTEMS
LOFT REACTOR
MODIFICATIONS
PWR TYPE REACTORS
REACTOR PROTECTION SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
SEISMIC EFFECTS
STRESS ANALYSIS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS