Effect of temperature on the fracture toughness in the nuclear reactor pressure vessel steel (SA508-3)

Conference · Sat Dec 31 04:00:00 EST 1994

OSTI ID:433626

Oh, S W; Lim, M B ^[1]; Yoon, H K ^[2]

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1. Dong-A Univ., Pusan (Korea, Republic of)
2. Dong-Eui Univ., Pusan (Korea, Republic of)

The elastic-plastic fracture toughness J{sub IC} of the Nuclear Reactor Pressure Vessel Steel (SA508-3) which has high toughness was obtained at three temperatures (room temperature, {minus}20 C, 200 C) using a 1/2 CT specimen. Especially the two methods recommended in ASTM and JSME were compared. It was found that difficulty exists in obtaining J{sub IC} by ASTM R-curve method, while JSME R-curve method yielded good results. The stretched zone width method gave slightly larger J{sub IC} values than those by the R-curve method for SA508-3 steel and the blunting line was not affected by the test temperatures. The relation between SZW and J, SZW and J/E and SZW and J/{sigma}{sub ys} before initiation of a stable crack growth in the fracture toughness test at three temperatures is described.

• OSTI ID: 433626
• Report Number(s): CONF-940409--; ISBN 1-880653-10-9
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
CRACK PROPAGATION
FRACTURE PROPERTIES
LOW ALLOY STEELS
MATERIALS TESTING
NUCLEAR FACILITIES
PRESSURE VESSELS