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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.
G. Neale Kelly, Martial Olast, Jaak Sinnaeve
Nuclear Technology | Volume 94 | Number 2 | May 1991 | Pages 161-176
Technical Paper | Advances in Reactor Accident Consequence Assessment / Nuclear Reactor Safety | doi.org/10.13182/NT91-A34539
Articles are hosted by Taylor and Francis Online.
The Commission of the European Communities, within the framework of its 1980–1984 radiation protection research program, initiated a 2-yr project in 1983 entitled “Methods for Assessing the Radiological Impact of Accidents” (MARIA). This project was continued and enlarged within the 1985–1989 research program. The main objectives of the project are (a) to develop a new probabilistic accident consequence assessment code that is modular, incorporates the best features of those codes already in use, can be readily modified to take account of new data and model developments, and is broadly applicable within the European Communities; (b) to acquire a better understanding of the limitations of current models and to develop more rigorous approaches where necessary; and (c) to quantify the uncertainties associated with the model predictions. Approximately 120 person-yr of effort have been committed to the second phase of the project, which involves contractors from 12 different organizations and institutes in the European Communities. This has led to the development of the accident consequence code COSYMA (COde SYstem from MARIA), which will be made generally available in mid-1990. The numerous and diverse studies that have been undertaken in support of this development are described, together with indications of where further effort might be most profitably directed.