Analysis of LOFT steam generator main feed piping loop seal modification

Technical Report · Tue Feb 14 04:00:00 EST 1978

DOI:https://doi.org/10.2172/5152210· OSTI ID:5152210

Nitzel, M. E.

The stress analysis is presented for the proposed loop seal modification to the LOFT Steam Generator Main Feed Piping. THE SAP IV finite element computer program was used to analyze normal, upset, emergency, and faulted conditions. Results of the analysis indicate that the modified main feed piping system will satisfy all structural adequacy criteria specified in Subarticle NC-3650 of the ASME Boiler and Pressure Vessel Code. Results also show that the isolation snubber configuration, specified in LTR 115-11, will also be adequate for the piping configuration analyzed.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 5152210
• Report Number(s): LTR-115-38; RE-A-78-015
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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LOFT REACTOR
MODIFICATIONS
PIPELINES
PWR TYPE REACTORS
REACTORS
RESEARCH AND TEST REACTORS
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STEAM GENERATORS
STRESS ANALYSIS
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WATER MODERATED REACTORS