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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Latest News
IAEA to help monitor plastic pollution in the Galapagos Islands
The International Atomic Energy Agency announced that its Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative has partnered with Ecuador’s Oceanographic Institute of the Navy (INOCAR) and Polytechnic School of the Coast (ESPOL) to build microplastic monitoring and analytical capacity to address the growing threat of marine microplastic pollution in the Galapagos Islands.
Won-Jin Cho, Sangki Kwon
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 245-256
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT12-A13369
Articles are hosted by Taylor and Francis Online.
The effects of the resaturation process occurring in the buffer on the analysis of temperature distribution in the engineered barrier system of a nuclear waste repository were assessed. The assessment was performed using the TOUGH2 computer code, which analyzes the multidimensional fluid and heat flows of the multiphase, multicomponent fluid mixture in an unsaturated medium. The hydraulic and thermal properties of the buffer, backfill, and near-field rock were measured and were used as input parameters for the analysis. If the resaturation process is considered in the thermal analysis, the disposal density of nuclear waste can be increased up to 30% under the given thermal constraint and site condition. The hydrostatic pressure in the near-field rock will not have an important impact on the resaturation process.