ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
G. LaVergne, J. E. Robinson, J. G. Martel
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 12-22
Technical Paper | Reactor | doi.org/10.13182/NT75-A24400
Articles are hosted by Taylor and Francis Online.
The matching of D-T fusion breeders to heavy-water CANDU-type reactors has been studied using the transport code ANISN to evaluate the neutron transport and breeding characteristics of a low-power-gain fusion blanket. The fusion blanket consists of a niobium structure, natural lithium coolant, and a graphite reflector with 2- to 6-cm-thick zones of Th, ThO2, or ThC situated between the first wall and the reflector. Total breeding ratios of 1.40 to 1.50 have been calculated. Using the calculated breeding ratios, a system period of less than 10 years is determined for proposed solid thorium fuels. The reaction rate ratio of fusion to fission is less than unity.
