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Fusion Science and Technology
Latest News
NEA irradiation system ready to deploy at MITR
A new irradiation experimental system is ready for deployment. The rig, which is the focus of In-Core Real-Time Mechanical Testing of Structural Materials (INCREASE-I), an OECD Nuclear Energy Agency project, will be used to conduct stress-relaxation tests of stainless steel at the Massachusetts Institute of Technology Reactor (MITR), according to the OECD NEA.
Tetsuya Suzuki, Toyohiko Yano, Tsutomu Mori, Hiroyuki Miyazaki, Takayoshi Iseki
Fusion Science and Technology | Volume 27 | Number 3 | May 1995 | Pages 314-325
Technical Paper | Materials Engineering | doi.org/10.13182/FST95-A30393
Articles are hosted by Taylor and Francis Online.
Neutron irradiation uniformly produces vacancies and interstitials in silcon carbide (SiC) poly crystals, and the specimen swells by 1 to 3%. Subsequent isochronal annealing leads to annihilation of the defects by the interstitial-vacancy recombination from around irradiation temperature, resulting in the shrinkage of the specimen. This shrinkage can be detected by measuring the specimen length with a conventional micrometer and its lattice parameter with an X-ray diffractometer. Furthermore, defect formation and annihilation affect the electrical resistivity and create paramagnetic centers caused by unpaired electrons. Helium atoms can be uniformly introduced into SiC utilizing the nuclear reaction of 10B(n, α)7 Li. By subsequent annealing above ∼1300°C, helium atoms with high vibration energy capture thermal vacancies to reduce the internal pressure and form bubbles at grain boundaries. The formation of helium bubbles accompanies a large volume expansion with increasing temperature, controlled by Greenwood et al.'s mechanism. The presence of helium bubbles at the grain boundaries promotes diffusional creep at lower temperatures (1300°C). Changes in physical properties by neutron irradiation are presented and discussed with respect to microstructures.