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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
G7 pledges support for nuclear at Italy meeting
The Group of Seven (G7) recommitted its support for nuclear energy in the countries that opt to use it at a Ministerial Meeting on Climate in Italy last month.
In a statement following the April meeting, the group committed to support multilateral efforts to strengthen the resilience of nuclear supply chains, referencing the goal set by 25 countries during last year’s COP28 climate conference in Dubai to triple global nuclear generating capacity by 2050.
W. Van Snyder
Nuclear Technology | Volume 209 | Number 11 | November 2023 | Pages 1840-1858
Note | doi.org/10.1080/00295450.2023.2205551
Articles are hosted by Taylor and Francis Online.
In April 1961, Atomic Power Development Associates (APDA) produced the “Summary of the APDA Fuel Development Programs.” Chapter XVII described a paste fuel concept. The report noted that there are “advantages inherent in a mobile-fueled reactor.” Patent number 3,169,117, entitled “Nuclear Reactor Paste Fuel Composition,” was issued on May 9, 1961. In May 1964, Argonne National Laboratory produced the “Catalog of Nuclear Reactor Concepts.” The chapter concerning paste fuels concluded: “The few paste-fuel concepts developed to date and the present early stages of such developments show that considerably more work probably will be required before the paste-fuel concept can be considered for commercial development.” This monograph enlarges upon and quantifies the APDA concept, which appears not to have been pursued. Additional passive safety concepts that might also eliminate the need for control assemblies are described. Several important consequences of continuously processed fuel that are not discussed in the APDA report are described in this paper, in particular, that the “iodine pit” startup control instability can be eliminated.