End-of-life examinations of Light Water Breeder Reactor grids and other module structural components (LWBR Development Program)

Technical Report · Thu Oct 01 00:00:00 EDT 1987

DOI:https://doi.org/10.2172/5447940· OSTI ID:5447940

Smith, B. C. ^[1]; Clayton, J. C.; Pitcairn, T. N.; Richardson, K. D.; Smith, B. C.; Wargo, J. E.

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1. ed.

End-of-Life examinations were performed on LWBR core structural components which had important influence on mechanical stability of fuel elements duing core performance. These components included: (1) AM-350 stainless steel grid sections to assess corrosion, stress relaxation, braze performance, and dimensional stability; (2) a 348 stainless steel flux thimble tube which failed in service; (3) various Inconel X-750, Inconel-600, 17-4 PH, and AM-350 bolts; (4) Zircaloy-4 module shells and screws; (5) Inconel-600 module cover plates and baseplates; (6) 304 stainless steel Bypass Inlet Flow Supply Tube; (7) 17-4 PH shear keys and Inconel-600 struts; (8) Zircaloy-4 module support posts; (9) seed module support shaft and balance piston. Examinations included visual inspection and, in some cases, dye penetrant and metallography. Threaded fasteners remained uncracked to end-of-life (EOL). Grid dimensions showed minor changes at EOL. Grid springs exhibited good stress relaxation characteristics. Corrosion resistance of core components was adequate, and components were relatively free from crud buildup.

• Research Organization: Bettis Atomic Power Lab. (BAPL), West Mifflin, PA (United States)
• DOE Contract Number: AC11-76PN00014
• OSTI ID: 5447940
• Report Number(s): WAPD-TM-1607; ON: DE88006921
• Resource Relation: Other Information: Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
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REACTOR COMPONENTS
SERVICE LIFE
CORROSION
EVALUATION
POST-IRRADIATION EXAMINATION
CORROSION RESISTANCE
DEPOSITS
EXPERIMENTAL DATA
FAILURES
FUEL ELEMENTS
INCONEL 600
INCONEL X750
INSPECTION
MECHANICAL PROPERTIES
MODULAR STRUCTURES
PHYSICAL RADIATION EFFECTS
REACTOR CORES
STABILITY
STAINLESS STEEL-304
STAINLESS STEEL-348
STRESS RELAXATION
ZIRCALOY 4
ALLOYS
BREEDER REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DATA
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INCONEL ALLOYS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ADDITIONS
NIOBIUM ALLOYS
NUMERICAL DATA
RADIATION EFFECTS
REACTORS
RELAXATION
STAINLESS STEELS
STEELS
THERMAL REACTORS
TIN ALLOYS
TITANIUM ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210500* - Power Reactors
Breeding
360105 - Metals & Alloys- Corrosion & Erosion
360103 - Metals & Alloys- Mechanical Properties
360106 - Metals & Alloys- Radiation Effects