Bias and precision of T0 values determined using ASTM Standard E 1921-97 for nuclear reactor pressure vessel steels

ASTM Special Technical Publication

Volumn , Issue 1366, 2000, Pages 143-161

  Kirk, Mark ^a   Lott, Randy ^a   Server, William L ^b   Hardies, Robert ^c   Rosinski, Stan ^d  

^a WESTINGHOUSE ELECTRIC COMPANY   (United States)

^b ATI Consulting   (United States)

^c Baltimore Gas & Electric Co   (United States)

^d ELECTRIC POWER RESEARCH INSTITUTE   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; DATABASE SYSTEMS; FERRITE; FRACTURE TOUGHNESS; NUCLEAR POWER PLANTS; NUCLEAR REACTORS; PRESSURE VESSEL CODES; RADIATION EFFECTS; STEEL STRUCTURES; THERMAL EFFECTS;

MASTER CURVE APPROACH; REACTOR PRESSURE VESSELS;

STEEL TESTING;

EID: 0034481934     PISSN: 10403094     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (24)

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