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
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!
Latest Magazine Issues
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
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.
Martin Knight, Paul Bryce, Sheldon Hall
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 398-408
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19428
Articles are hosted by Taylor and Francis Online.
This paper describes a method of analyzing pressurized water reactor UO2/mixed oxide (MOX) cores with the lattice code WIMS and the reactor code PANTHER. "Embedded supercells," run within the reactor code, are used to correct the standard methodology of using two-group smeared data from single-assembly (SA) lattice calculations. In many other codes the weakness of this standard approach has been improved for MOX by imposing a more realistic environment in the lattice code or by improving the sophistication of the reactor code. In this approach an intermediate set of calculations is introduced, leaving both lattice and reactor calculations broadly unchanged.The essence of the approach is that the whole core is broken down into a set of embedded supercells, each extending over just four quarter assemblies, with zero leakage imposed at the assembly midlines. Each supercell is solved twice, first with a detailed multigroup pin-by-pin solution and then with the standard SA approach. Correction factors are defined by comparing the two solutions, and these can be applied in whole-core calculations.The restriction that all such calculations be modeled with zero leakage means that they are independent of each other and of the core-wide flux shape. This allows parallel precalculation for the entire cycle once the loading pattern has been determined, in much the same way that SA lattice calculations can be precalculated once the range of fuel types is known.Comparisons against a whole-core pin-by-pin reference demonstrates that the embedding process does not introduce a significant error, even after burnup and refueling. Comparisons against a WIMS reference demonstrate that a pin-by-pin multigroup diffusion solution is capable of capturing the main interface effects.This therefore defines a practical approach for achieving results close to lattice code accuracy but broadly at the cost of a standard reactor calculation.