Test methodology and technology of fracture toughness for small size specimens
Creators
- 1. Japan Atomic Energy Agency, Naga-gun, Ibaraki-ken (Japan)
- 2. JNE Techno-Research Co., Kanagawa-ken (Japan)
Description
Full text of publication follows: Small specimen test technology (SSTT) is required to investigate mechanical properties in the limited availability of effective irradiation volumes in test reactors and accelerator-based neutron and charged particle sources. The test methodology guideline and the manufacture processes for very small size specimens have not been established, and we would have to formulate it. The technology to control exactly the load and displacement is also required in the test technology under the environment of high dose radiation produced from the specimens. The objective of this study is to examine the test technology and methodology of fracture toughness for very small size specimens. A new bend test machine installed in hot cell has been manufactured to obtain fracture toughness and DBTT (ductile - brittle transition temperature) of reduced-activation ferritic/martensitic steels for small bend specimens of t/2-1/3PCCVN (pre-cracked 1/3 size Charpy V-notch) with 20 mm length and DFMB (deformation and fracture mini bend specimen) with 9 mm length. The new machine can be performed at temperatures from -196 deg. C to 400 deg. C under unloading compliance method. Neutron irradiation was also performed at about 250 deg. C to about 2 dpa in JMTR. After the irradiation, fracture toughness and DBTT were examined by using the machine. Checking of displacement measurement between linear gauge of cross head's displacement and DVRT of the specimen displacement was performed exactly. Conditions of pre-crack due to fatigue in the specimen preparation were also examined and it depended on the shape and size of the specimens. Fracture toughness and DBTT of F82H steel for t/2-1/3PCCVN, DFMB and 0.18DCT specimens before irradiation were examined as a function of temperature. DBTT of smaller size specimens of DFMB was lower than that of larger size specimen of t/2-1/3PCCVN and 0.18DCT. The changes of fracture toughness and DBTT due to irradiation were also examined, and brittle behavior was observed at temperatures between -125 deg. C and -175 deg. C in the irradiated t/2-1/3PCCVN specimen. The increase of maximum loads due to irradiation was observed.(authors)
Availability note (English)
Available in abstract form only, full text entered in this recordAdditional details
Publishing Information
- Imprint Pagination
- 1 p.
- Report number
- INIS-FR--09-0592
Conference
- Title
- 13. International Conference on Fusion Reactor Materials
- Acronym
- ICFRM-13
- Dates
- 10-14 Dec 2007
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40067870
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCELERATORS; ATOMIC DISPLACEMENTS; DUCTILE-BRITTLE TRANSITIONS; FATIGUE; FERRITIC STEELS; FRACTURE PROPERTIES; FRACTURES; HOT CELLS; IRRADIATION; LENGTH; MARTENSITIC STEELS; NEUTRONS; RADIATION DOSES; TEMPERATURE DEPENDENCE; TEST REACTORS
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; DIMENSIONS; DOSES; ELEMENTARY PARTICLES; EQUIPMENT; FAILURES; FERMIONS; HADRONS; IRON ALLOYS; IRON BASE ALLOYS; LABORATORY EQUIPMENT; MECHANICAL PROPERTIES; NUCLEONS; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; STEELS; TEST FACILITIES; TRANSITION ELEMENT ALLOYS