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
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!
Latest Magazine Issues
Jul 2024
Jan 2024
Latest Journal Issues
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.
Kenneth W. Downes, Anita Court
Nuclear Technology | Volume 3 | Number 7 | July 1967 | Pages 399-405
Technical Paper and Note | doi.org/10.13182/NT67-A27837
Articles are hosted by Taylor and Francis Online.
These studies were performed for the purpose of determining whether simple fuel alteration could lead to improved performance of neutron beam experiments at light-water-moderated reactors of the Bulk Shielding Facility (BSF) type. Thermal-neutron beams from split cores and a standard BSF core were characterized. Data were normalized to the standard core. For a split core with a 4-in. gap, the ratio of thermal neutrons-to-fast neutrons was improved by a factor of 6.6 ± 0.3 over that in a standard core; the ratio of thermal neutrons-to-gamma rays was improved by a factor of 2.9 ± 0.1 over that in a standard core. The thermal-neutron beam intensity was 67% of the value obtained from the standard core. Reactivity characteristics of split cores with a 4-in. gap were also investigated as a function of size. In an assembly with a built-in excess k of > 2.5%, it was found that one section of the core could be taken critical independent of the position of control rods in the other section.