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.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
August 2025
Fusion Science and Technology
Latest News
Ho Nieh nominated to the NRC
Nieh
President Trump recently nominated Ho Nieh for the role of commissioner in the Nuclear Regulatory Commission through the remainder of a term that will expire June 30, 2029.
Nieh has been the vice president of regulatory affairs at Southern Nuclear since 2021, though he is currently working as a loaned executive at the Institute of Nuclear Power Operations, where he has been for more than a year.
Nieh’s experience: Nieh started his career at the Knolls Atomic Power Laboratory, where he worked primarily as a nuclear plant engineer and contributed as a civilian instructor in the U.S. Navy’s Nuclear Power Program.
From there, he joined the NRC in 1997 as a project engineer. In more than 19 years of service at the organization, he served in a variety of key leadership roles, including division director of Reactor Projects, division director of Inspection and Regional Support, and director of the Office of Nuclear Reactor Regulation.
M. P. Paulsen, B. E. Griebenow, L. R. Feinauer, J. H. McFadden, Peter J. Jensen
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 274-288
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34141
Articles are hosted by Taylor and Francis Online.
The RETRAN-02 transient thermal-hydraulic analysis program has found wide acceptance by the nuclear utility industry for performing analyses of operational transients and small-break loss-of-coolant accidents. There are, however, known limitations with RETRAN-02 and the Electric Power Research Institute has sponsored the development of RETRAN-03 to address these limitations. The major objectives of the development program are (a) to extend the range of analyses that can be performed with RETRAN, (b) to make the code more dependable and faster running, and (c) to have a more transportable code. Summaries of the RETRAN-02 models that have been modified for RETRAN-03, new models that have been added, and the new semi-implicit steady-state and dynamic solution methods are presented. The primary development task associated with improving the transportability of the code dealt with implementing the IBM and CDC environmental libraries (assembly language) using a common FORTRAN 77 source. The salient results of this work are discussed.