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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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ANS standard updated for determining meteorological information at nuclear facilities
Following approval in October from the American National Standards Institute, ANSI/ANS-3.11-2024, Determining Meteorological Information at Nuclear Facilities, was published in late November. This standard provides criteria for gathering, assembling, processing, storing, and disseminating meteorological information at commercial nuclear power plants, U.S. Department of Energy/National Nuclear Security Administration nuclear facilities, and other national or international nuclear facilities.
Gasper Zerovnik, Luka Snoj, Matjaz Ravnik
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 183-190
Technical Paper | doi.org/10.13182/NSE163-183
Articles are hosted by Taylor and Francis Online.
We demonstrated the use of combinatorial methods to optimize the filling of spent nuclear fuel (SNF) in metal canisters for final deep SNF repository, according to the maximal allowed thermal power per canister Pmax and the limit of n = 4 spent-fuel assemblies per canister. As a next step, the deposition time can be optimized by minimizing the required number of canisters M and the interim storage time. The method has been tested in detail for a typical pressurized water reactor (PWR), nuclear power plant (NPP) Krsko, SNF for different numbers of reactor cycles and different Pmax. The results show that the time interval between the last reactor cycle and the optimal deposition time varies between 3 and 30 yr for a typical PWR. The most significant contribution to the uncertainty of the calculated SNF decay heat (thermal power) is due to inaccurate cross sections taken from generic cross-section libraries. The quality of the results was verified by comparing the calculated M to the theoretical lower boundary Mmin. The idea behind the optimization method is universal and thus can be implemented for any SNF, canister, and repository design.