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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.
M. E. Sawan
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1431-1436
Blanket Neutronic | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A39967
Articles are hosted by Taylor and Francis Online.
Nuclear analysis for the array of loops ICRF launcher module design of INTOR is presented. The nuclear radiation environment in the different module components is determined. The fast neutron fluence in the BeO radome is 1022 n/cm2 after one full power year leading to significant microcracking. Activation calculations for SF6 imply a total activity of 5 × 104 Ci at shutdown. Nuclear heating results in a large , breakdown rate in SF6. A 1.6 m thick nuclear shield is needed to allow for hands-on maintenance one day after shutdown behind the launcher module. The results imply that significant design changes are required for the array of loops ICRF launcher module to stand the severe INTOR nuclear environment.
