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Division Spotlight
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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
C.Ahnert, J. M. Aragonés , A. Crespo, A. Labay, J. R. León, A. I. Alvarez
Nuclear Science and Engineering | Volume 100 | Number 3 | November 1988 | Pages 305-313
Technical Paper | doi.org/10.13182/NSE88-A29044
Articles are hosted by Taylor and Francis Online.
The advances achieved during 1986 in the development and validation of the Spanish pressurized water reactor (PWR) core analysis system SEANAP-86 are presented and discussed. The advances were achieved through the cooperation of two research institutes (DENIM and JEN-CIEMAT) and two nuclear power plants (Almaraz and Ascó). The main features and advances of the core analysis system are summarized. The system is intended to provide the utilities with the in-house capability to analyze the core design, nuclear tests, and operation along reload cycles, as technical support for licensing and operation. The validation is done by an extensive comparison with the measurements available from the nuclear tests and in-core operation followup of four 900-MW(electric) PWR units (Almaraz-1 and -2, Ascó-1 and -2) along their first cycles and several reload cycles, as well as with the available design data. Good agreement is obtained for the broad sets of parameters and cycles analyzed, which qualifies the SEANAP-86 system as an effective core analysis support tool and encourages further developments, which are presently under way.