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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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NN Asks: What did you learn from ANS’s Nuclear 101?
Mike Harkin
When ANS first announced its new Nuclear 101 certificate course, I was excited. This felt like a course tailor-made for me, a transplant into the commercial nuclear world. I enrolled for the inaugural session held in November 2024, knowing it was going to be hard (this is nuclear power, of course)—but I had been working on ramping up my knowledge base for the past year, through both my employer and at a local college.
The course was a fast-and-furious roller-coaster ride through all the key components of the nuclear power industry, in one highly challenging week. In fact, the challenges the students experienced caught even the instructors by surprise. Thankfully, the shared intellectual stretch we students all felt helped us band together to push through to the end.
We were all impressed with the quality of the instructors, who are some of the top experts in the field. We appreciated not only their knowledge base but their support whenever someone struggled to understand a concept.
Venkata V. R. Venigalla, Miles Greiner
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 313-324
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A8966
Articles are hosted by Taylor and Francis Online.
A two-dimensional finite volume mesh of a legal-weight truck cask cross section is constructed, including four pressurized water reactor fuel assemblies inside. Computational fluid dynamics (CFD) simulations calculate buoyancy-driven gas motion, natural convection and radiation heat transfer in geometrically accurate gas-filled fuel regions, and conduction within the solid components. Steady-state simulations are performed with the cask in a normal transportation environment for ranges of fuel heat generation rate and cladding emissivity, with atmospheric-pressure helium or nitrogen cover gases. The cask thermal dissipation capacity is defined as the fuel heat generation rate that brings the fuel cladding temperature to its allowed limit. That capacity is 23% higher when helium is the cover gas than for nitrogen. Increasing the cladding emissivity by 10% increases the capacity by 4% for nitrogen, but only 2% for helium. Stagnant-gas simulations using the geometrically accurate mesh predict essentially the same cask thermal dissipation capacity as simulations that include gas motion. This indicates that buoyancy-induced gas motion is not strong enough to significantly enhance heat transfer for this configuration. Simulations employing effective thermal conductivities and homogenized (nongeometrically accurate) meshes in the fuel regions predict cask thermal capacities that are 3 to 8% lower than the geometrically accurate CFD simulations. Basket surface temperatures calculated in this work will be used as boundary conditions in future benchmark experiments.