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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
Toru Hiraoka, Kiyoshi Sako, Hideki Takano, Takeshi Ishii, Mitsuru Sato
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 305-329
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34526
Articles are hosted by Taylor and Francis Online.
A high-breeding fast reactor with fission product gas purge/tube-in-shell metallic fuel assemblies is proposed. Its reactor doubling time is <10 yr because fast reactors must have economical fuel breeding as well as economical electricity generation. The core has a high volume fraction of fuel (>50%) and realizes a very hard neutron spectrum. Thus, a fast-breeding 670-MW(electric) reactor with a high breeding ratio (1.84) and a short reactor doubling time (6.7 yr) is proposed. The structure of the fuel assembly, its fabrication, and the fission product gas purging mechanism are assessed and the new fuel assembly concept is determined to be feasible. Purging of the fission product gas does not affect the shielding requirement and can be managed by a small-scale cover gas treatment system because of the good fission product retention characteristics of the sodium in the fuel assemblies. The entire reactor configuration, including the intermediate heat exchangers, was assessed utilizing conventional reactor components.