Energy Technology Engineering Center (ETEC): Annual technical progress report, January-December 1986

Technical Report · Thu Apr 30 00:00:00 EDT 1987

DOI:https://doi.org/10.2172/713633· OSTI ID:713633

Information is presented on: creep ratchetting; stress indices tee; elastic followup test; reactor shutdown system - CRD bellows; natural circulation testing; SAFR RACS cavity inspection; PRISM seismic testing; PRISM EM pump testing; SASS jet pump testing; NRC seismic pipe testing; NRC valve performance; helical coil steam generator; steam generator leak dynamics; steam generator leak dynamics; steam generator leak detection and location; 9Cr-1Mo sodium exposure tests; In-vessel pressure and flow instrumentation; sodium pressure measurement; sodium level measurement; rotatable plug seal; fiber optics; lithium diode development; and space/terrestrial reactors - SP-100.

• Research Organization: Rockwell International Corp., Canoga Park, CA (United States). Energy Technology Engineering Center
• Sponsoring Organization: USDOE
• DOE Contract Number: AC03-76SF00700
• OSTI ID: 713633
• Report Number(s): ETEC-87-1; ON: TI87027723
• Resource Relation: Other Information: PBD: 30 Apr 1987
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
STEAM GENERATORS
HEAT EXCHANGERS
VALVES
PUMPS
IN-SERVICE INSPECTION
REACTOR MATERIALS
PIPES
TESTING
PERFORMANCE
CHROMIUM-MOLYBDENUM STEELS
CREEP
RATCHETING
LEAKS
NATURAL CONVECTION
STRESSES
ELASTICITY
REACTOR SHUTDOWN
FLUID-STRUCTURE INTERACTIONS
TEST FACILITIES
SODIUM
HEAT TRANSFER
HYDRAULICS
RESEARCH PROGRAMS
REACTOR PROTECTION SYSTEMS
SEISMIC EFFECTS
FIBER OPTICS
SPACE POWER REACTORS