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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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!
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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.
Kwang-Il Ahn, Hee-Dong Kim
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 132-144
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3082
Articles are hosted by Taylor and Francis Online.
Continuous efforts to identify and better understand the uncertainties have changed many model parameters and physical phenomena employed in the phenomenological transient models or related computer codes to be estimated by more detailed models. Since their true forms are often not known, however, different modeling assumptions have resulted in various forms of model elements even for a given phenomenon, allowing for different results in the code predictions. In a situation in which there are no rigorous ways to decide the credibility of a specific model element over another, these different model elements can become additional contributors to an overall uncertainty of the physical model predictions. In recent times, most uncertainty analyses of physical models have been focused on the model parameters, without considering the impact of these different model elements. Such levels of uncertainty analysis can only explore a subspace of the true uncertainty space of physical models, and thus the resultant uncertainty tends to underestimate the magnitude of possible uncertainties. Regarding the modeling sources of uncertainty, on the other hand, a model sensitivity analysis has been conventionally utilized to assess the effects of each model element on the code predictions. However, such types of analysis cannot systematically account for synergistic effects of all constituent model elements on the code predictions. A formal procedure is provided for characterizing probabilistically two different sources of uncertainty addressed in the phenomenological transient models (i.e., parametric and modeling sources) and their statistical propagation to obtain the overall uncertainties in the physical model predictions.