Effect of neutron irradiation on the mechanical properties of weld overlay cladding for reactor pressure vessel
Source abstract
Abstract
Abstract This study investigates the effects of high fluence neutron irradiation on the mechanical properties of two types of cladding materials fabricated using the submerged-arc welding and electroslag welding methods. The tensile tests, Charpy impact tests, and fracture toughness tests were conducted before and after the neutron irradiation with a fluence of 1 × 1024 n/m2 at 290 °C. With neutron irradiation, we could observe an increase in the yield strength and ultimate strength, and a decrease in the total elongation. All cladding materials exhibited ductile-to-brittle transition behavior during the Charpy impact tests. A reduction in the Charpy upper-shelf energy and an increase in the ductile-to-brittle transition temperature was observed with neutron irradiation. There was no obvious decrease in the elastic–plastic fracture toughness (JIc) of the cladding materials upon irradiation with high neutron fluence. The tearing modulus was found to decrease with neutron irradiation; the submerged-arc-welded cladding materials exhibited low JIc values at high temperatures.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (20)
Show source-provided references
1. Japan Electric Association Code committee, Method of Verification Tests of the Fracture Toughness for Nuclear Power Plants Components, JEAC 4206-2007, 2007 (in Japanese).
2. Japan Society of Mechanical Engineers, Codes for nuclear power generation facilities -rules on fitness-for-service for nuclear power plants-, JSME S NA1-2012, 2012 (in Japanese).
3. U.S. Nuclear Regulatory Commission Regulations, Alternate Fracture Toughness Requirements for Protection, Against Pressurized Thermal Shock Events, Title 10, Code of Federal Regulations, Part 50, Section 50.61a, 2010.
4. Association Francaise pour les Regles de Conception et de Construction des Chaudieres Electro, In-service Inspection Rules for Mechanical Components of PWR Nuclear Islands, RSE-M, 2010.
5. Brooks · Inter. Mater. Rev. · 1991 · 36 · 1610.1179/imr.1991.36.1.16 ↗
6. Corwin · J. Gray Nucl. Eng. Des. · 1985 · 89 · 19910.1016/0029-5493(85)90155-4 ↗
7. Corwin · Nucl. Eng. Des. · 1987 · 98 · 17110.1016/0029-5493(87)90165-8 ↗
8. Haggag · Nucl. Eng. Des. · 1990 · 118 · 29710.1016/0029-5493(90)90031-R ↗
9. Haggag · Nucl. Eng. Des. · 1990 · 124 · 12910.1016/0029-5493(90)90359-6 ↗
10. Haggag · NUREG/CR-6363 ORNL/TM-13047 · 1997
11. Nishiyama · JAERI – Res. · 2000 · 2000–47
12. M. Horsten, P. Belcher, Effects of Radiation on Materials: 20th International Symposium, ASTM STP 1405, 2001, p. 328.10.1520/STP10542S ↗
13. M. Bethmont et al., IAEA Specialist Meeting on Irradiation Embrittlement and Mitiglation, 1995.
14. American Standard for Testing and Materials, Standard Test Method for Measurement of Fracture Toughness, ASTM E1820-11, 2011.
15. H.A. Ernst, Materials Resistance and Instability Beyond J-Controlled Crack Growth, Elastic–Plastic Fracture, ASTM STP 803, vol. I, ASTM, Philadelphia, 1983, pp. 191–213.10.1520/STP37294S ↗
16. Takeuchi · J. Nucl. Mater. · 2011 · 415 · 19810.1016/j.jnucmat.2011.06.004 ↗
17. Takeuchi · J. Nucl. Mater. · 2014 · 449 · 27310.1016/j.jnucmat.2014.01.004 ↗
18. Takeuchi · J. Nucl. Mater. · 2012 · 425 · 6010.1016/j.jnucmat.2011.12.004 ↗
19. American Standard for Testing and Materials, Standard test method for determining J–R curves, ASTM E1152-87, 1988.
20. European Structural Integrity Society, Procedure for Determining the Fracture Behavior of Materials, ESIS P2-92, 1992.