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

ASTM Special Technical Publication

Volumn STP 1405, Issue , 2001, Pages 79-96

  Onizawa, Kunio ^a   Suzuki, Masahide ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

fracture toughness; irradiation embrittlement; lower bound; master curve; precracked Charpy; reactor pressure vessel; structural integrity; surveillance

Indexed keywords

ANNEALING; BRITTLE FRACTURE; DUCTILE FRACTURE; FRACTURE TESTING; MATERIALS TESTING; NEUTRON IRRADIATION; PRESSURE VESSELS; PRESSURIZED WATER REACTORS; TEMPERATURE;

CHARPY-V; IRRADIATION EMBRITTLEMENT; LOW BOUND; MASTER-CURVE; PRECRACKED; PRECRACKED CHARPY; REACTOR PRESSURE VESSEL; REFERENCE TEMPERATURE; SURVEILLANCE; TEMPERATURE SHIFT;

FRACTURE TOUGHNESS;

EID: 85164974033     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/STP10527S     Document Type: Conference Paper

References (18)

1. ASME Boiler and Pressure Vessel Code, Section XI, "Inservice Inspection of Nuclear Power Plant, " American Society for Mechanical Engineers, 1995.
2. Japanese Electric Association, "Methods of Surveillance Tests for Structural Materials of Nuclear Reactors, " JEAC 4201-1991. (in Japanese)
3. Nanstad, R. K., Haggag, F. M., McCabe, D. E., Iskander, S. K., Bowman, K. O., and Menke, B. H., "Irradiation Effects on Fracture Toughness of Two High-Copper Submerged-arc Welds, HSSI Series 5, "NUREG/CR-5913 Vol.1, U.S.NRC, October 1992.
4. Miglin, M. T., Oberjohn, L. A., and Van Der Sluys, W. A., "Analysis of Results from the MPC/JSPS Round Robin Testing Program in the Ductile-to-Brittle Transition Region, " Fracture Mechanics: Twenty-fourth Volume, ASTMSTP 1207, J.D. Landes, D. E. McCabe and J. A. M. Boulet, Eds., American Society for Testing and Materials, Philadelphia, 1994, pp. 342-354.
5. Iwadate, T., Tanaka, Y., Ono, S., and Watanabe, J., "An Analysis of Elastic-Plastic Fracture Toughness Behavior for Jic Measurement in the Transition Region, " Elastic-Plastic Fracture: Second Symposium, Volume II-Fracture Resistance Curves and Engineering Applications, ASTMSTP 803, C. F. Shi and J. P. Gudas, Eds., American Society for Testing and Materials, 1983, pp. 11-531-II-561.
6. Server, W. et al., "Application of Master Curve Fracture Toughness Methodology for Ferritic Steels, " EPRI TR-108390, Electric Power Research Institute, April 1998.
7. Server, W. L. and Rosinski, S. T., "Technical Basis for Application of the Master Curve Approach to Reactor Pressure Vessel Integrity Assessment, " Effects of Radiation on Materials: 19"" International Symposium, ASTMSTP 1366, M. L. Hamilton, A. S. Kumar, S. T. Rosinski, and M. L. Grossbeck, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2000.
8. 0 Values Determined Using ASTM Standard El 921-97 for Nuclear Reactor Pressure Vessel Steels, " Effects of Radiation on Materials: 19"" International Symposium, ASTMSTP 1366, M. L. Hamilton, A. S. Kumar, S. T. Rosinski, and M. L. Grossbeck, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2000.
9. Onizawa, K. and Suzuki, M., "JAERI's Contribution to the IAEA Coordinated Research Programme on 'Assuring Structural Integrity of Reactor Pressure Vessels' (CRP-IV), - Final Report -, " JAERI-Research 2000-022, Japan Atomic Energy Research Institute, May 2000.
10. CRP Sub-Committee, "Manufacturing History and Mechanical Properties of Japanese Materials Provided for The International Atomic Energy Agency, " Japan Welding Engineering Society, Oct. 1986.
11. Onizawa, K., Suzuki, M., and Ueda, S., "JAERI Contribution for the IAEA Coordinated Research Program Phase III on Optimizing of Reactor Pressure Vessel Surveillance Programmes and Their Analysis, " JAERI-M 93-201, Japan Atomic Energy Research Institute, October 1993.
12. Onizawa, K., Tobita, T., and Suzuki, M., "Investigation on the Evaluation of Cleavage Fracture Toughness Using PCCv Specimens in the Ductile-Brittle Transition Range of Reactor Pressure Vessel Steels, " JAERI-Research 97-081, Japan Atomic Energy Research Institute, November 1997.
13. th International Symposium, ASTMSTP 1366, M. L. Hamilton, A. S. Kumar, S. T. Rosinski, and M. L. Grossbeck, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2000.
14. JSPS 129 Committee, "Standard Test Method for Fracture Toughness within Ductile-Brittle Transition Range, " Japan Society for Promoting Science, 1995.
15. Chaouadi, R., "Fracture Toughness Measurements in the Transition Regime Using Small Size Samples, " Small Specimen Test Techniques, ASTMSTP 1329, W. R. Corwin, S. T. Rosinski, and E. van Walle, Eds., American Society for Testing and Materials, 1998, pp. 214-237.
16. Wallin, K., "Validity of Small Specimen Fracture Toughness Estimates Neglecting Constraint Corrections, " Constraint Effects in Fracture Theory and Applications: Second Volume, ASTMSTP 1244, M. Kirk and Ad Bakker, Eds. American Society for Testing and Materials, 1995.
17. th International Conference on Structural Mechanics in Reactor Technology, Korea, August 1999, IV-137.
18. ASME Code Case N-629, "Use of Fracture Toughness Test Data to Establish Reference Temperature for Pressure Retaining Materials for Section XI."