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!
Latest Magazine Issues
Jul 2024
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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.
A. E. Pickett, W. L. Pearl, M. C. Rowland
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 453-461
Technical Paper | doi.org/10.13182/NT65-A20557
Articles are hosted by Taylor and Francis Online.
Nonsensitized Type-304 stainless-steel fuel cladding cracked intergranularly when exposed to high-temperature, high-purity, water reactor environments. Similar failures were produced out of reactor in stressed tubular-capsule specimens exposed to dilute solutions of iron chloride, copper chloride, sodium hydroxide, and chromic acid at 650° F (343°C). An iron chloride test was developed that closely simulates the intergranular attack on stressed nonsensitized Type-304 stainless-steel fuel cladding. Stressed, cold-worked, nonsensitized Type-304 stainless-steel tubing cracked in less than 24 h at 650° F when exposed to ferric-ferrous chloride solutions containing only 40 Cl parts/106 and 4 soluble-iron parts/106. Exposure at 650° F caused intergranular cracking only, while exposure at 550° F (288° C) caused mixed transgranular and intergranular cracking. The accelerated autoclave test can be used for screening of prospective cladding materials and alloy modifications and developing a better understanding of the mechanism of attack.
