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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
When your test capsule is the test: ORNL’s 3D-printed rabbit
Oak Ridge National Laboratory has, for the first time, designed, printed, and irradiated a specimen capsule—or rabbit capsule—for use in its High Flux Isotope Reactor (HFIR), the Department of Energy announced on January 15.
M. Nakano, H. Tsunoda, J. Hirota
Nuclear Science and Engineering | Volume 87 | Number 3 | July 1984 | Pages 283-294
Technical Paper | doi.org/10.13182/NSE84-A17783
Articles are hosted by Taylor and Francis Online.
An experimental study has been made on FCA Assembly VIII-2 to test the validity of the calculational method for the reactivity effect due to axial displacement of fuel and cladding. The emphasis was placed on the systematic measurement of reactivity change and flux distribution in simple configurations rather than the simulation of a possible accident sequence. The analysis was made using the Japan Atomic Energy Research Institute Fast Set Version II. The transport calculation with an S4P0 approximation predicts both the reactivity change and the fission rates of 235U and 238U fairly well, although there still remains the trend of underestimation of reactivity effect, which increases with expansion of the fuel slumping to the core edge.
