ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
H. S. Bailey, R. N. Evatt, G. L. Gyorey, C. P. Ruiz
Nuclear Technology | Volume 17 | Number 3 | March 1973 | Pages 217-224
Technical Paper | Fuel | doi.org/10.13182/NT73-A31265
Articles are hosted by Taylor and Francis Online.
An evaluation of the radiation from higher exposure light water reactor fuel that is of significance in shipping container design has been made. Because these fuels contain significant quantities of transplutonium nuclides, it has been established that the neutron emission rate and the associated biological dose rate are of large enough magnitude to require special consideration in the shielding design. This analysis is based on experimental determination of heavy element nuclide concentrations in both PWR and BWR fuels and the use of ANISN-type shielding calculations. The results indicate that a conventional cask would not have sufficient neutron shielding capability to permit shipment of spent fuel with exposures in excess of ∼22 000 MWd/MT. Hence, a new generation of shipping casks with specific provisions for neutron shielding is required.
