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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Holger Seher, Guido Bracke, Gerd Frieling, Ingo Kock (GRS)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 35-40
The TOUGH2 code was modified by GRS with several repository-relevant processes (called TOUGH2-GRS) and used as a code for simulating multi-phase flow in porous media. For code development and quality assurance, an extensive program was implemented to demonstrate the correctness and reliability of TOUGH2-GRS.
The LLW/ILW repository “Endlager für radioaktive Abfälle Morsleben (ERAM)” located in Saxony-Anhalt, Germany, was chosen to evaluate the impact of grid complexity on the results obtained by two-phase flow calculations with TOUGH2-GRS for C-14. Three grids with increasing complexity regarding spatial resolution and including multiple mine levels were generated and compared with single-phase-flow calculations with parameter datasets for ERAM, taken from the application for its decommissioning, which is currently under review.
The discharge of relevant nuclides is in all cases below the discharge modeled by single-phase simulations. The calculated discharge of C-14 depends on the complexity of model grids. The highest release of C-14 was calculated for the grid with medium complexity for a scenario with significant brine entry.