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
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
S. Chatzidakis, A. Ikonomopoulos, S. E. Day
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 119-131
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13332
Articles are hosted by Taylor and Francis Online.
This study presents numerical modeling of the SPERT-IV D-12/25 tests, a series of reactivity insertion, self-limiting, transients for a variety of coolant flow conditions. The PARET-ANL code is used to simulate the system response under these reactivity-initiated accident conditions and estimate the measured damage-indicating parameters - including the cladding temperature - using three departure from nucleate boiling (DNB) correlations, namely, those of Tong, Mirshak, and Bernath. The main objective of this sensitivity analysis is to identify, through performance measures, the DNB correlation influence on the prediction of the transient behavior. It appears that for reactivity insertions >1.20 $, the predicted transient behavior varies significantly depending on the applied DNB correlation. In addition, this study discusses the degree of conservatism introduced by each DNB correlation in the peak clad temperature estimates.
