Irradiation creep deformation of modified 316 and 15Cr-20Ni base austenitic fuel elements irradiated in FFTF

Institution of Chemical Engineers Symposium Series

Volumn , Issue 148, 2000, Pages 487-499

  Uehira, Akihiro ^a   Ukai, Shigeharu ^a   Mizuta, Syunji ^a   Puigh, Raymond J ^a  

^a Sumitomo Metal Industries Limited   (Japan)

Author keywords

Austenitic stainless steel; Core material; Fast breeder reactor; FFTF; Fuel pin; Irradiation creep

Indexed keywords

BREEDER REACTORS; CREEP; FAST REACTORS; IRRADIATION; NUCLEAR FUEL ELEMENTS; PRESSURE EFFECTS; STAINLESS STEEL; SWELLING;

FAST BREEDER REACTORS; FUEL PINS;

AUSTENITE;

EID: 0034461059     PISSN: 03070492     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (14)

1. Development of long life FBR core materials
2. Development of long life FBR fuels with particular emphasis on cladding material improvement and fuel fabrication
3. Development of long life FBR core materials
4. The effects of phase stability on void swelling in P, Ti-modified 316 stainless steels during neutron irradiation
5. The swelling behavior of titanium-stabilized austenitic steels used as structural materials of fissile subassemblies in phenix
6. Irradiation performance of cladding and structural steels in liquid metal reactors
7. Cessation of irradiation creep in AISI 316 concurrent with high level of swelling
8. A third stage of irradiation creep involving its cessation at high neutron exposures
9. The relationship between swelling and irradiation creep in 20% cold-worked 316 stainless steel
10. Irradiation creep of 11Cr-0.5Mo-2W,V,Nbferritic-martensitic, modified 316, and 15Cr-20Ni austenitic S. S. irradiated in FFTF to 103-206 dpa
11. Irradiation performance of FBR monju-type fuel with modified type 316 stainless steel at high burnup
12. Swelling and irradiation creep of neutron-irradiated 316Ti and 15-15Ti steels
13. Irradiation creep due to SIPA under cascade damage conditions