Margins for an in-plant piping system under dynamic loading
Conference
·
OSTI ID:5785695
The objective of this study is to verify that piping designed according to current practice does indeed have a large margin against failure and to quantify the excess capacity for piping and dynamic pipe supports on the basis of data obtained in a series of high-level seismic experiments (designated SHAM) on an in-plant piping system at the HDR (Heissdampfreaktor) Test Facility in Germany. 4 refs., 6 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5785695
- Report Number(s):
- ANL/CP-72611; CONF-910602-37; ON: DE91011842
- Resource Relation:
- Conference: American Society of Mechanical Engineers (ASME) pressure vessels and piping conference, San Diego, CA (USA), 23-27 Jun 1991
- Country of Publication:
- United States
- Language:
- English
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+1 more
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
NUCLEAR POWER PLANTS
PIPES
DYNAMIC LOADS
SEISMIC EFFECTS
HDR REACTOR
REACTOR SAFETY
RESPONSE FUNCTIONS
RESTRAINTS
STANDARDS
STRESS ANALYSIS
STRESSES
SUPPORTS
TEST FACILITIES
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
FUNCTIONS
MECHANICAL STRUCTURES
NUCLEAR FACILITIES
POWER PLANTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
THERMAL POWER PLANTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories
NUCLEAR POWER PLANTS
PIPES
DYNAMIC LOADS
SEISMIC EFFECTS
HDR REACTOR
REACTOR SAFETY
RESPONSE FUNCTIONS
RESTRAINTS
STANDARDS
STRESS ANALYSIS
STRESSES
SUPPORTS
TEST FACILITIES
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
FUNCTIONS
MECHANICAL STRUCTURES
NUCLEAR FACILITIES
POWER PLANTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
THERMAL POWER PLANTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories