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From renaissance to reality: Infrastructure for a global nuclear fuel cycle
Dale Klein
This article was adapted from the author’s speech during a plenary at the 21st International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2025), San Antonio, Texas, July 2025.
There has been a lot of discussion lately about reforming the Nuclear Regulatory Commission. But I want to be clear: When it comes to nuclear safety and security, there is no place for partisan politics. I support efforts to streamline regulatory processes, but the independence and integrity of the NRC must remain sacrosanct. If we are serious about expanding nuclear power and reclaiming our global leadership in nuclear technology, having a strong independent regulator is fundamental.
Right now, we’re on the edge of a global nuclear resurgence driven by rising demand from data centers, growing concerns about energy security, and the need to decarbonize industry.
Attila Kiss, Attila Aszódi
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 40-53
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9444
Articles are hosted by Taylor and Francis Online.
Computational fluid dynamics (CFD) codes have become promising tools for the investigation of thermal hydraulics in revolutionary reactor concepts in the last decade. In Reynolds-averaged Navier-Stokes calculations, the CFD codes (for example, the ANSYS CFX code used here) use turbulence modeling, wall functions, and other approaches. Therefore, the accuracy of CFD codes for water flow under supercritical conditions has to be examined. The first aim of this work is to investigate the effects of different material property definition methods on the numerical results obtained with CFX code. The second aim is to assess the accuracy of the conventional turbulence models (such as k-, k-, and SST) under supercritical water conditions. The results and comparison of three independent validations for supercritical water flow in vertical smooth-bore tubes with upward flow direction are presented in this paper. It is well known that the material properties strongly depend on the temperature and the pressure near and above the thermodynamic critical point. It is demonstrated that rather than analytical or discrete point methods, the IAPWS-IF97 material table best represents the strongly changing material properties. A nonaxialsymmetric effect on result fields was not found based on the three validations; therefore, a rotational periodic or two-dimensional grid approach is recommended for further validations of homogenously heated, vertically installed, smooth-bore straight tubes cooled by supercritical water. The calculation results have been compared with measurements, and the computational errors for the three validations were found to be in the ranges of 0 to 25%, 0 to 18%, and 2 to 40% for the Swenson, Yamagata, and Herkenrath experiments, respectively. The results of the three validations indicate the need to improve a turbulence model to take into account the buoyancy effect on the turbulence for thermal-hydraulic calculations of the supercritical water.