Piping system response during high-level simulated seismic tests at the Heissdampfreaktor Facility: (SHAM Test Facility)

Technical Report · Wed Jul 01 04:00:00 EDT 1992

OSTI ID:7232923

Steele, R Jr; Nitzel, M E ^[1]

---

1. EG and G Idaho, Inc., Idaho Falls, ID (United States)

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.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: NRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 7232923
• Report Number(s): NUREG/CR-5646; EGG--2655; ON: TI92018773
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
BWR TYPE REACTORS
COMPUTER CODES
CONTROL EQUIPMENT
DYNAMIC LOADS
ENRICHED URANIUM REACTORS
EQUIPMENT
EXPERIMENTAL REACTORS
FLOW REGULATORS
HDR REACTOR
PERFORMANCE
PIPES
POWER REACTORS
REACTORS
RESEARCH AND TEST REACTORS
SEISMIC EFFECTS
TESTING
THERMAL REACTORS
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS