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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.
Jorge H. Barón, Jorge E. Núñez McLeod, Selva S. Rivera
Nuclear Technology | Volume 134 | Number 2 | May 2001 | Pages 97-109
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3189
Articles are hosted by Taylor and Francis Online.
Construction of the CAREM-25 full-size prototype, a very low power nuclear power station [25 MW(electric)], is scheduled to begin in Argentina in 2001. The CAREM-25 is designed based on principles of inherent safety, passive safety functions, and ease of operation. This paper analyzes the safety philosophy from the point of view of risk by performing a level-III probabilistic safety assessment (PSA) of this prototype. The specific PSA steps are discussed, including a specially developed method to obtain representative initiating events, system analysis by fault trees, event development in event trees, plant and containment response analysis, containment event tree development, consequence calculations, and risk representation. The PSA results are presented and discussed in terms of their own values as well as in comparison to other PSA results performed for larger nuclear power plants (NPPs). The advantages of the CAREM-25 from the risk point of view are studied in terms of the effective reduction of both the probability of severe accident sequences and the potential consequences of such sequences (radiological and emergency preparedness impact). The risk point of view also provides a perspective to analyze the impact of several design modifications in order to further reduce the residual risk of the NPP. These design modifications, several of which have already been included in the prototype, are discussed and evaluated.