ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Alice Ying, Hongjie Zhang, Mu-Young Anh, Youngmin Lee
Fusion Science and Technology | Volume 68 | Number 2 | September 2015 | Pages 346-352
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-908
Articles are hosted by Taylor and Francis Online.
First-of-a-kind numerical simulation was performed to evaluate time dependent tritium transport properties for Korea’s HCCR (Helium-Cooled Ceramic Reflector) TBM (Test Blanket Module) design under ITER inductive operating conditions. The estimation of tritium inventories in various components of the HCCR submodule and its permeation amount into the helium coolant was obtained through three computational models involving: 1) a 3D FW standalone model where diffusion and permeation into FW He coolant through tritium ion implantation was studied, 2) a 2D Poloidal-Radial (P-R) mid-plane model where the effect of increased tritium concentration in the purge gas stream was accounted for, and 3) a 2D Toroidal-Radial (T-R) mid-plane model to study tritium concentration accumulation in the He coolant. The analysis shows that tritium inventory in the breeder reaches an equilibrium value in about 10 cycles, and is about 0.373 mg per submodule. Tritium inventory in the ferritic steel structure reaches its equilibrium value in less than 10 cycles, and has about 0.0012 mg per submodule at the end of the plasma burn. The amount of the tritium permeated into helium coolant is about 1.8% of the amount of tritium produced per cycle.