Fracture mechanics investigation of reactor pressure vessel steels by means of sub-sized specimens. KLEINPROBEN. Final report
Creators
Contributors
Description
The embrittlement of reactor pressure vessel (RPV) steels due to neutron irradiation restricts the operating lifetime of nuclear reactors. The reference temperature π0, obtained from fracture mechanics testing using the Master Curve concept, is a good indicator of the irradiation resistance of a material. The measurement of the shift in π0 after neutron irradiation, which accompanies the embrittlement of the material, using the Master Curve concept, enables the assessment of the reactor materials. In the context of worldwide life time extensions of nuclear power plants, the limited availability of neutron irradiated materials (surveillance materials) is a challenge. Testing of miniaturized 0.16T C(T) specimens manufactured from already tested standard Charpy-sized specimens helps to solve the material shortage problem. In this work, four different reactor pressure vessel steels with different compositions were investigated in the unirradiated and in the neutron-irradiated condition. A total number of 189 mini-C(T) samples were fabricated and tested. An important component of this study is the transferability of fracture mechanics data from mini-C(T) to standard Charpy-sized specimen. Our results demonstrate good agreement of the reference temperatures from the mini-C(T) specimens with those from standard Charpy-sized specimens. RPV steels containing higher Cu and P contents exhibit a higher increase in π0 after irradiation. The fracture surfaces were investigated using SEM in order to record the location of the fracture initiators. The fracture modes were also determined. A large number of test results formed the basis for a censoring probability function, which was used to optimally select the testing temperature in Master Curve testing. The effect of the slow stable crack growth censoring criteria from ASTM E1921 on the determination of π0 was analysed and found to have a minor effect. Our results demonstrate the validity of mini-C(T) specimen testing and confirm the role of the impurity elements Cu and P in neutron embrittlement. We anticipate further research linking microstructure to the fracture properties of materials before and after neutron irradiation and the optimization of Master Curve testing using the results from our statistical analysis.
Additional details
Additional titles
- Original title (German)
- Bruchmechanische Untersuchung von ReaktordruckbehΓ€lterstΓ€hlen mittels Kleinprobentechnik. KLEINPROBEN. Abschlussbericht
Identifiers
Publishing Information
- Imprint Pagination
- 62 p.
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CHARPY TEST; CRACK PROPAGATION; EMBRITTLEMENT; FRACTURE MECHANICS; FRACTURE PROPERTIES; IRRADIATION; MATERIALS TESTING; MICROSTRUCTURE; NUCLEAR POWER PLANTS; OPTIMIZATION; PRESSURE VESSELS; REACTOR MATERIALS; REACTOR VESSELS; STEEL-MNNIMO; STEEL-NIMOCR; STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CONTAINERS; DESTRUCTIVE TESTING; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IMPACT TESTS; IRON ALLOYS; IRON BASE ALLOYS; LOW ALLOY STEELS; MANGANESE ALLOYS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; MECHANICS; MOLYBDENUM ADDITIONS; MOLYBDENUM ALLOYS; NICKEL ADDITIONS; NICKEL ALLOYS; NUCLEAR FACILITIES; POWER PLANTS; STEELS; TESTING; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS
Optional Information
- Contract/Grant/Project number
- BMUV 1501592B
- Funding organization
- Bundesministerium fΓΌr Umwelt, Naturschutz, nukleare Sicherheit und Verbraucherschutz (BMUV), Bonn (DE)