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
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
November 2025
Fusion Science and Technology
Latest News
The progress so far: An update on the Reactor Pilot Program
It has been about three months since the Department of Energy named 10 companies for its new Reactor Pilot Program, which maps out how the DOE would meet the goal announced by executive order in May of having three reactors achieve criticality by July 4, 2026.
Thomas Croisette, Paolo Olita, Claire Vaglio-Gaudard, Pablo Rubiolo, Raphaël Préa
Nuclear Science and Engineering | Volume 199 | Number 12 | December 2025 | Pages 2110-2128
Research Article | doi.org/10.1080/00295639.2025.2502888
Articles are hosted by Taylor and Francis Online.
This paper illustrates the first steps of the Best Estimate Plus Uncertainty methodology implemented for the study of a main steam line break (MSLB) accident in a four-loop pressurized water reactor. An MSLB is characterized by rapid depressurization of a steam generator, leading to uncontrolled cooling of the primary circuit and a core power increase because of moderator reactivity feedback. The phenomenology of this accident is multiphysics as it involves strong coupling between reactor physics and thermal hydraulics.
First, a Phenomena Identification and Ranking Table (PIRT) was established based on expert judgment to list all the main physical phenomena involved in the accident and rank them according to their influence on the physical quantity of interest: the minimum departure from nucleate boiling ratio (MDNBR). The PIRT analysis resulted in a list of 10 dominant phenomena and 10 uncertain parameters associated with such phenomena. Then, a one-at-a-time sensitivity analysis was performed for all the dominant phenomena identified in the PIRT. Based on such analysis, three phenomena emerged as the most influential: water mixing in the lower plenum, initial reactivity margin, and moderator reactivity feedback. The sensitivity analysis provided a better understanding of the accident sequence and allowed slightly revising and consolidating the PIRT. It also showed that the axial power profile plays an important role in determining the MDNBR value. Last, an uncertainty propagation study was realized on the MSLB transient based on the Monte Carlo method. Probability density functions (PDFs) of the uncertain parameters were estimated according to expert judgment. The study led to the evaluation of a lower bound of the quantity of interest, i.e. the MDNBR, by applying the Wilks method. Possibilities for improvement were also identified, and an inverse uncertainty quantification process based on measurement data is proposed to improve the estimation of PDFs associated with uncertain parameters.