Energy Technology Engineering Center (ETEC) annual technical progress report, January-December 1985

Technical Report · Wed Apr 30 00:00:00 EDT 1986

DOI:https://doi.org/10.2172/711948· OSTI ID:711948

Information is presented on: creep ratchetting; steam generator leak dynamics; natural circulation testing; fuel transfer cell mockup; stress indices tee; elastic followup test; NaK-to-Air heat exchanger; NRC valve performance; subscale shrouded inducer substitution pump test; DHRS venturi test; over temperature actuated reactor shutdown system; 9 Cr - 1 Mo sodium exposure tests; helical coal steam generator; NDHX cleaning; steam generator leak detection and location; in-service inspection; fragility test facility; sodium pressure measurement; and sodium level measurement.

• Research Organization: Rockwell International Corp., Canoga Park, CA (United States). Energy Technology Engineering Center
• Sponsoring Organization: USDOE
• DOE Contract Number: AC03-76SF00700
• OSTI ID: 711948
• Report Number(s): ETEC-86-1; ON: TI86026362
• Resource Relation: Other Information: PBD: 30 Apr 1986
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
LMFBR TYPE REACTORS
STEAM GENERATORS
HEAT EXCHANGERS
VALVES
PUMPS
IN-SERVICE INSPECTION
REACTOR MATERIALS
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