Tensile and burst tests in support of the cadmium safety rod failure evaluation
The reactor safety rods may be subjected to high temperatures due to gamma heating after the core coolant level has dropped during the ECS phase of hypothetical LOCA event. Accordingly, an experimental safety rod testing subtask was established as part of a task to address the response of reactor core components to this accident. This report discusses confirmatory separate effects tests conducted to support the evaluation of failures observed in the safety rod thermal tests. As part of the failure evaluation, the potential for liquid metal embrittlement (LME) of the safety rod cladding by cadmium (Cd) -- aluminum (Al) solutions was examined. Based on the test conditions, literature data, and U-Bend tests, its was concluded that the SS304 safety rod cladding would not be subject to LME by liquid Cd-Al solutions under conditions relevant to the safety rod thermal tests or gamma heating accident. To confirm this conclusion, tensile tests on SS304 specimens were performed in both air and liquid Cd-Al solutions with the range of strain rates, temperatures, and loading conditions spanning the range relevant to the safety rod thermal tests and gamma heating accident.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 5300586
- Report Number(s):
- WSRC-RP-92-314; ON: DE92015892
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ACCIDENTS
ALLOYS
ALUMINIUM
AUSTENITIC STEELS
CADMIUM
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CONTROL ELEMENTS
CORROSION RESISTANT ALLOYS
DUCTILITY
ELEMENTS
EMBRITTLEMENT
FAILURES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LOSS OF COOLANT
MATERIALS
MECHANICAL PROPERTIES
METALS
NICKEL ALLOYS
REACTOR ACCIDENTS
REACTOR COMPONENTS
SCRAM RODS
STAINLESS STEEL-304
STAINLESS STEELS
STEEL-CR19NI10
STEELS
STRAIN RATE
TENSILE PROPERTIES
220400* -- Nuclear Reactor Technology-- Control Systems
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ACCIDENTS
ALLOYS
ALUMINIUM
AUSTENITIC STEELS
CADMIUM
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CONTROL ELEMENTS
CORROSION RESISTANT ALLOYS
DUCTILITY
ELEMENTS
EMBRITTLEMENT
FAILURES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LOSS OF COOLANT
MATERIALS
MECHANICAL PROPERTIES
METALS
NICKEL ALLOYS
REACTOR ACCIDENTS
REACTOR COMPONENTS
SCRAM RODS
STAINLESS STEEL-304
STAINLESS STEELS
STEEL-CR19NI10
STEELS
STRAIN RATE
TENSILE PROPERTIES