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Division Spotlight
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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.
Claudia M. Abbate, John W. Craig
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 755-758
Technical Paper | TMI-2: Decontamination and Waste Management / Radioactive Waste Management | doi.org/10.13182/NT89-A27668
Articles are hosted by Taylor and Francis Online.
Until recently, the U.S. Nuclear Regulatory Commission (NRC) inspection effort as it applied to transportation casks focused on the written quality assurance (QA) program of cask vendors and subcontractors and U.S. Department of Transportation documentation requirements rather than the implementation of the QA program during the fabrication of the casks. The focus during these inspections has now shifted from a “paper” review to a safety review by a more thorough examination of equipment and the implementation of the QA program during the fabrication of components such as transportation casks. This revised approach to inspections performed by the NRC is reflected in the recent vendor inspections of the defueling canisters and two transportation casks that were designed and manufactured for defueling and transporting the Three Mile Island Unit 2 debris. These inspections identified deficiencies in the fabrication process, and the vendor’s corrective actions resulted in improved controls and an improved product. The transportation of radioactive material will increase in years to come, and it is the responsibility of those who design, fabricate, and use the casks to ensure that a high level of safety is maintained, the requirements are met, and a cask of high quality is used.