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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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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.
Kazumi Iwamoto
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 189-199
Technical Paper | doi.org/10.13182/NSE64-A18318
Articles are hosted by Taylor and Francis Online.
Irradiated UO2 graphite fuel samples in which most of the fission products had recoiled into the graphite matrix were heated after irradiation, and then leached with nitric acid. The leach-ability of non-gaseous fission products was influenced by fission product concentration, by irradiation temperature, and largely by temperature and period of the heating. A possible rate-controlling mechanism for the fission product loss during the heating is discussed, and the results obtained are compared with some of the earlier work. The data may be interpreted as indicating that the fission products migrate through the graphite crystal to its surface according to a fast and a slow migration step. Escape from the graphite matrix by volatilization is apparently less rapid than the fast migration step; volatilization may be the rate-limiting mechanism in the loss process.
