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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.
Fujio Maekawa, Yujiro Ikeda, Yuriy M. Verzilov, Chikara Konno, Masayuki Wada, Hiroshi Maekawa, Yukio Oyama, Yoshitomo Uno
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1081-1087
Neutronics Experiments and Analyses | doi.org/10.13182/FST96-A11963094
Articles are hosted by Taylor and Francis Online.
To assess validity of the shielding design tools for ITER, the benchmark experiment on SS316/Water shield conducted at FNS/JAERI is analyzed. As far as a simple bulk shield of SS316/Water is concerned, the followings are found assuming that no uncertainty is involved in the response functions of the design parameters. Nuclear data bases of JENDL Fusion File and FENDL/E-1.0 are valid to predict all the design parameters with uncertainties less than a factor of 1.25. At the connection legs between shield blanket modules and back plates, both MCNP and DOT calculations can predict helium production rate with uncertainties less than 10 %. For the troidal field coils on the midplane, all the nuclear parameters can be predicted with uncertainties less than a factor of 1.25 by MCNP and DOT with consideration of self-shielding correction of cross sections and energy group structure of 125-n and 40-γ. The uncertainties for toroidal field coils are considerably smaller than the design margins secured to the shielding designs under ITER/EDA.
