Comparison of transition temperature shifts between static fracture toughness and charpy-v impact properties due to irradiation and post-irradiation annealing for Japanese A533B-1 steels

Institution of Chemical Engineers Symposium Series

Volumn , Issue 148, 2000, Pages 79-96

  Onizawa, Kunio ^a   Suzuki, Masahide ^a  

^a NONE

Author keywords

Fracture toughness; Irradiation embrittlement; Lower bound; Master curve; Precracked Charpy; Reactor pressure vessel; Structural integrity; Surveillance

Indexed keywords

EMBRITTLEMENT; FRACTURE TOUGHNESS; IMPACT TESTING; NEUTRON IRRADIATION;

REACTOR PRESSURE VESSELS (RPV);

PRESSURE VESSELS;

EID: 0034459318     PISSN: 03070492     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (18)

1. ASME boiler and pressure vessel code, section XI
2. Analysis of results from the MPC/JSPS round robin testing program in the ductile-to-brittle transition region
3. IC measurement in the transition region
4. Technical basis for application of the master curve approach to reactor pressure vessel integrity assessment
5. 0 values determined using ASTM standard E1921-97 for nuclear reactor pressure vessel steels
6. Effect of irradiation on fracture toughness in the transition range of RPV steels
7. Fracture toughness measurements in the transition regime using small size samples
8. Validity of small specimen fracture toughness estimates neglecting constraint corrections
9. Fracture toughness evaluation by precracked Charpy specimens in the transition temperature range of RPV steels