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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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.
Yuji Ishiguro
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 121-126
Technical Note | Fuel Cycle | doi.org/10.13182/NT83-A33150
Articles are hosted by Taylor and Francis Online.
A new concept of fueling a liquid-metal fast breeder reactor (LMFBR) is proposed with the aims of increasing the resource base of nuclear energy for the generation of electricity and of resolving the safety question of current LMFBRs. The basic feature of the concept is the use of 233U/Th fuel in a central part of the LMFBR core and Pu/U fuel in the outer core. The reactor is flexible in its utilization of nuclear fuels and can be an efficient breeder reactor with either the uranium or the thorium cycle. The safety characteristics of the reactor are superior to those of plutonium-fueled LMFBRs of current designs with the sodium-void reactivities being negative almost everywhere in the core. The design and thermal characteristics of the proposed pins indicate that in the 233U/Th-fueled inner core, thick soft-spectrum pins can be advantageous over solid pins of a more conventional type.