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Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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.
Ch. Cavagna, O. Gastaldi, L. Martin, V. Grabon
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 274-281
Technical Note | Sodium Technology - Thermal Hydraulics | doi.org/10.13182/NT06-A3707
Articles are hosted by Taylor and Francis Online.
As part of the renovation project of the Phénix plant, the modular-type steam generators were the subject of an expert evaluation program in order to verify their condition after ~100 000 h of power operation and demonstrate their ability to continue operation for the planned lifetime extension (30 000 h).This evaluation, based on the destructive examination of several modules, showed that some parts of the superheater and reheater were affected by some delayed reheat cracking of 321 H stainless steel. Thus, the extension of the operation of the units for the prolonged lifetime of the plant could not be justified.A major repair operation was undertaken. Every superheater and reheater module was disassembled. A cleaning process was developed for removal of residual sodium inside the modules, based on the water vapor nitrogen method, and adapted to the special geometry of the component. The potentially defective parts were replaced by new ones. A specific procedure was used for welding of aged to new materials. The nonreplaced parts were controlled by a specially developed ultrasonic technique; 47 modules were successfully repaired within 1 yr.