Piping system response during high-level simulated seismic tests at the Heissdampfreaktor Facility: (SHAM Test Facility)
Creators
- 1. EG and G Idaho, Inc., Idaho Falls, ID (United States)
Description
The SHAM seismic research program studied the effects of increasing levels of seismic excitation on a full-scale, in situ nuclear piping system containing a naturally aged United States (US) 8-in. motor-operated gate valve. The program was conducted by Kernforschungszentrum Karlsruhe at the Heissdampfreaktor near Frankfurt, Germany. Participants included the United States, Germany, and England. Fifty-one experiments were conducted, with the piping supported by six different piping support systems, including a typical stiff US piping support system of snubbers and rigid struts. This report specifically addresses the tests conducted with the US system. The piping system withstood large displacements caused by overload snubber failures and local piping strains. Although some limit switch chatter was observed, the motor operator and valve functioned smoothly throughout the tests. The results indicate that sufficient safety margins exist when commonly accepted design methods are applied and that piping systems will likely maintain their pressure boundary in the presence of severe loading and the loss of multiple supports
Availability note (English)
MF available from INIS under the Report Number; OSTI as TI92018773; NTIS; INIS; GPO.
Files
Additional details
Publishing Information
- Imprint Pagination
- 218 p.
- Report number
- NUREG/CR--5646
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24011826
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; DYNAMIC LOADS; HDR REACTOR; PERFORMANCE; PIPES; SEISMIC EFFECTS; TESTING; VALVES
- Descriptors DEC
- BWR TYPE REACTORS; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; EXPERIMENTAL REACTORS; FLOW REGULATORS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).
- Secondary number(s)
- EGG--2655.