Comparison of irradiation creep and swelling of an austenitic alloy irradiated in FFTF and PFR

Conference · Fri Oct 01 00:00:00 EDT 1999

OSTI ID:679517

Garner, F A ^[1]; Toloczko, M B ^[2]; Munro, B; Adaway, S ^[3]; Standring, J ^[4]

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1. Battelle Pacific Northwest Lab., Richland, WA (United States)
2. Washington State Univ., Pullman, WA (United States)
3. AEA Technology (United Kingdom)
4. UKAEA (United Kingdom)

comparative irradiation of identically constructed creep tubes in the Fast Flux Test Facility (FFTF) and the Prototypic Fast Reactor (PFR) shows that differences in irradiation conditions arising from both reactor operation and the design of the irradiation vehicle can have a significant impact on the void swelling and irradiation creep of austenitic stainless steels. In spite of these differences, the derived creep coefficients fall within the range of previously observed values for 316 SS.

• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-96OR22464
• OSTI ID: 679517
• Report Number(s): CONF-960643-; TRN: 99:009450
• Resource Relation: Conference: 18. symposium on effects of radiation on materials, Hyannis, MA (United States), 25-27 Jun 1996; Other Information: PBD: 1999; Related Information: Is Part Of Effects of radiation on materials: 18. international symposium; Nanstad, R.K. [ed.] [Oak Ridge National Lab., TN (United States)]; Hamilton, M.L.; Garner, F.A. [eds.] [Pacific Northwest National Lab., Richland, WA (United States)]; Kumar, A.S. [ed.] [Univ. of Missouri, Rolla, MO (United States)]; PB: 1261 p.; ASTM special technical publication 1325
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
COMPARATIVE EVALUATIONS
PHYSICAL RADIATION EFFECTS
CREEP
SWELLING
FFTF REACTOR
PFR REACTOR
STAINLESS STEEL-316
REACTOR EXPERIMENTAL FACILITIES
RADIATION DOSES