Published 1978
| Version v1
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Effects of multiple transients on fast reactor fuel pin cladding mechanical properties
Description
The effects of various TREAT and simulated transient events on subsequent burst strength of 20% cold worked AISI 316 irradiated fast reactor fuel pin cladding were evaluated. Cladding strength after transient exposure was compared to strength prior to transient exposure, using a HEDL correlation of failure temperatures with irradiation and test parameters. The simulated transients and post-transient strength tests were performed in the Fuel Cladding Transient Tester (FCTT), which was developed at HEDL to simulate cladding conditions during in-reactor transient events by pressurizing tubing specimens under transient heating conditions
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 7 p.
- Report number
- HEDL-SA--1598-FP
Conference
- Title
- 1978 winter meeting of American Nuclear Society.
- Dates
- 12 - 17 Nov 1978.
- Place
- Washington, DC, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10461754
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL CANS; LMFBR TYPE REACTORS; MECHANICAL PROPERTIES; PHYSICAL RADIATION EFFECTS; STAINLESS STEEL-316; THERMAL STRESSES; TRANSIENTS
- Descriptors DEC
- ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; RADIATION EFFECTS; REACTORS; STAINLESS STEELS; STEELS; STRESSES; TRANSITION ELEMENT ALLOYS
Optional Information
- Secondary number(s)
- CONF-781105--97.