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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.
F. Maekawa, C. Konno, K. Kosako, Y. Oyama, Y. Ikeda, H. Maekawa
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2107-2111
Blanket Shield and Neutronic | doi.org/10.13182/FST92-A30031
Articles are hosted by Taylor and Francis Online.
The fusion bulk shielding experiments on the cylindrical assemblies of 1.12 m in length and 1.20 m in diameter made of type 316 stainless steel have been carried out at the FNS facility in JAERI. This paper presents the analytical results for these experiments using the Sn code DOT3.5 and the Monte Carlo code MCNP with cross section libraries based on JENDL-3. The calculated results by both codes agree well with the measured values for threshold reactions and neutron energy spectra above 2 MeV. For the neutron energy spectra in keV energy region and fission rates of 235U, agreements between the measured data and the values by MCNP are pretty good, while the DOT3.5 calculation largely underestimated the measured values by a factor of 2–3 in deeper positions of the assemblies. For gamma-ray heating and gamma-ray spectra, relations between experiments and calculations are similar to those for low energy neutrons. A possible problem is pointed out in gamma-ray production processes when the DOT3.5 code and the FUSION-J3 library based on JENDL-3 are used.
