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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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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April 2024
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February 2024
Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Milan Vujović, Miloš Vujisić
Nuclear Technology | Volume 208 | Number 11 | November 2022 | Pages 1649-1665
Technical Paper | doi.org/10.1080/00295450.2022.2070354
Articles are hosted by Taylor and Francis Online.
Several select geopolymer, polymer, and composite materials are considered as potential candidates for the inner shielding in containers used for storage and disposal of low- and intermediate-level radioactive waste, from the perspective of radiation effects. The suitability of the probed materials is examined through Monte Carlo simulations, which yield absorbed dose values in container inner shieldings of various compositions and dimensions. The radioactive waste considered in the simulation models contains 60Co or 137Cs and is placed inside standard 216.5-L (55-gal) drums, in either compacted or solidified form. The influence of container stacking, in either a storage or a disposal environment, on the dose in the shielding is also taken into account. The simulation results are used for calculating the dose-dependent overpressure within the container caused by the gas generated in the inner shielding through radiolysis. Two types of waste activity limits are determined for each of the researched shielding materials: one below which the overpressure decreases after the initial heat-induced jump and another that results in an overpressure that stays just below the maximum tolerable value. Dose-dependent changes of the polymer and composite shielding materials’ molecular weights are also calculated. The obtained results show that with regard to the radiation effects caused by the investigated sources, the examined materials are compatible with the proposed use as inner shielding in radioactive waste containers.