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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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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From the pages of Nuclear News: Industry update November 2023
Here is a recap of industry happenings from the recent past:
Centrus-Oklo partnership expands
Oklo, a California-based developer of next-generation fission reactors, has expanded its partnership with Centrus Energy, a Maryland-based supplier of nuclear fuel and services. The two companies have been cooperating since 2021 on the development of Centrus’s American Centrifuge Plant in Piketon, Ohio, to produce high-assay low-enriched uranium (HALEU) fuel. According to the companies’ new memorandum of understanding, Centrus will manufacture certain components for Oklo’s Aurora “powerhouse” reactor, a fast neutron reactor designed to generate up to 15 MW of power and operate for at least 10 years without refueling. The Aurora is also designed to produce usable heat. Centrus also has agreed to purchase electricity generated by the Aurora reactors, while Oklo has agreed to purchase HALEU fuel from the Piketon facility. The facility is expected to begin fuel production before the end of the year.
Yaoli Zhang, Jacopo Buongiorno, Michael Golay, Neil Todreas
Nuclear Technology | Volume 203 | Number 2 | August 2018 | Pages 129-145
Technical Paper | doi.org/10.1080/00295450.2018.1433935
Articles are hosted by Taylor and Francis Online.
The Offshore Floating Nuclear Plant (OFNP) integrates an advanced light water reactor into a cylindrical, double-hull, floating platform. It offers a series of potential benefits in economics and safety. The 300-MW(electric) version, named OFNP-300, uses an ocean-based direct reactor auxiliary cooling system (DRACS) to remove decay heat from the core passively and indefinitely during loss of feedwater or loss of off-site power events. In the ocean, the OFNP platform may roll during storms or even statically tilt following asymmetric flooding of underwater compartments. The effects of rolling motion and static tilt on the engineered safety systems are investigated in this paper using a RELAP5-3D (version 4.3.4) model of OFNP-300. The oscillations of the platform are described as the superposition of sinusoidal motions for the six degrees of freedom, i.e., heave, roll, pitch, yaw, sway, and surge. The plant’s thermal-hydraulic responses to two postulated accidents, i.e., loss-of-coolant accident (LOCA) and station blackout (SBO), are then studied in three scenarios: (a) a design-basis 100-yr storm, (b) a bounding scenario in which the platform is assumed to pitch and roll with an amplitude of 20 deg, and (c) a bounding scenario in which the platform experiences a static tilt of 30 deg. The results of the RELAP5 analysis show that the safety margins of OFNP-300 are not challenged in the aforementioned three postulated scenarios. From a thermal-hydraulic point of view, the pitch and roll motions affect the flow in the DRACS but have no negative effect on the temperatures in the core during LOCA and SBO. Static platform tilt is tolerable up to 45 deg, beyond which the emergency core cooling system can no longer function.