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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Ding She, Zhihong Liu, Lei Shi
Nuclear Science and Engineering | Volume 185 | Number 2 | February 2017 | Pages 351-360
Technical Paper | doi.org/10.1080/00295639.2016.1272363
Articles are hosted by Taylor and Francis Online.
Dispersion fuel is used in high-temperature reactors (HTRs) and some other advanced reactors. It contains a stochastic mixture of microsphere fuel grains or burnable poison grains embedded in a matrix material, which leads to the so-called double heterogeneity problem in the neutron transport calculation. This work investigates an equivalent homogenization method to deal with the stochastic media. In this method, the stochastic media are transformed to a homogenized material by introducing spatial self-shielding factors and preserving first-collision probabilities. A transmission model is proposed to calculate the first-collision probabilities and the self-shielding factors. In addition, the method is extended to treat the stochastic media with multitype grains. The applicability and correction techniques for the proposed method are discussed. The proposed method has been implemented in a lattice physics code named XPZ for HTRs. Numerical results are presented for typical HTR fuel pebbles and are validated against Monte Carlo solutions. It is concluded that the proposed equivalent homogenization method is promising for treating the double-heterogeneity problem and can be conveniently implemented in existing lattice physics codes.