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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
Shigeru Tanaka, Masato Akiba, Masanori Araki, Masayuki Dairaku, Hiroshi Horiike, Takao Itoh, Mikito Kawai, Masao Komata, Masaaki Kuriyama, Shigeru Kitamura, Shinzaburo Matsuda, Mamoru Matsuoka, Kiyoshi Mizuhashi, Yutaka Ohuchi, Yoshihiro Ohara, Yoshikazu Okumura, Kiyoshi Shibanuma, Takemasa Shibata, Kazuhiro Watanabe, Russel P. Wells
Fusion Science and Technology | Volume 7 | Number 3 | May 1985 | Pages 391-398
Technical Paper | Magnet System | doi.org/10.13182/FST85-A24558
Articles are hosted by Taylor and Francis Online.
Influence of the magnetic field, which is produced around the JT-60 tokamak, on the performance of the neutral beam injector was experimentally studied using the stray field simulating coils installed around the prototype injector unit. Temperature distributions on the ion dump shifted vertically and the peak values changed in the presence of the field, as expected from the calculation of ion orbits. The shift length and the peak values remained within the permissible level, however, because of the operation of two cancellation coils, one of which was set around the reflecting magnet and another around the neutralizer magnetic shield. The neutral power injected into the beam target decreased by 4 to 5 % during application of the stray field due to the reionization loss of neutral particles. Under operating conditions, the heat load on each component was below the design value and all the components worked without any problems in the presence of stray magnetic field.