Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Transient and static mechanical properties of D9 fuel pin cladding and duct material irradiated to high fluence

Conference ·
OSTI ID:6979244
;  [1];  [2]
  1. Westinghouse Hanford Co., Richland, WA (USA)
  2. Pacific Northwest Lab., Richland, WA (USA)
+ Show Author Affiliations
Simulated transient tests and standard static mechanical property tests were performed on irradiated specimens of D9, a low-swelling, advanced austenitic stainless developed for fast reactor operation. Results of the transient tests were compared with existing data on 316 and HT9 stainless steels. The D9 alloy exhibited the same behavior attributed to the fuel adjacency effect (which is characterized by reduced strength and ductility as a result of cladding contact with oxide fuel) observed in 316 stainless steel. In the mechanical property tensile and fracture toughness tests, D9 exhibited a slightly lower fracture toughness than either HT9 or 316 stainless steel. Comparison of tensile strengths indicated that irradiated D9 is stronger than HT9, but slightly weaker than 316 stainless steel. The D9 alloy exhibited a lower tensile ductility than either 316 stainless steel or HT9. The D9 transient and mechanical properties data are now available for computer code analysis of D9 as a fast reactor fuel system material. 15 refs., 12 figs.
Research Organization:
Pacific Northwest Lab., Richland, WA (USA)
Sponsoring Organization:
DOE/ER
DOE Contract Number:
AC06-76RL01830
OSTI ID:
6979244
Report Number(s):
PNL-SA-17517; CONF-900623--14; ON: DE90016327
Country of Publication:
United States
Language:
English

Similar Records

Transient and static mechanical properties of D9 fuel pin cladding and duct material irradiated to high fluence
Conference · Sat Mar 31 23:00:00 EST 1990 · OSTI ID:6913782
Performance of titanium stabilized D9 cladding and ducts
Conference · Mon Mar 31 23:00:00 EST 1986 · OSTI ID:6555724
Advanced alloys for LMFBR fuel cladding and ducts
Conference · Wed Apr 18 23:00:00 EST 1984 · OSTI ID:5963014

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
AUSTENITIC STEELS
CLADDING
DAMAGING NEUTRON FLUENCE
DEPOSITION
DUCTILITY
FRACTURE PROPERTIES
FUEL ELEMENTS
FUEL PINS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
NEUTRON FLUENCE
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
STEELS
SURFACE COATING
TENSILE PROPERTIES