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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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.
Yuji Enokido, Sadamu Yamanouchi, Junji Komatsu, Toshiyuki Itaki
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 164-169
Technical Paper | Technique | doi.org/10.13182/NT83-A33311
Articles are hosted by Taylor and Francis Online.
A shielded ion microprobe analyzer for elemental and isotopic analyses of irradiated fast reactor fuel and fuel component has been developed and installed in an alpha-gamma hot cell. Radiation shielding of the equipment ensures the radiation dose of <2 mR/h (5.16 × 10−7 C/kg) for 5 Ci (1.85 × 1011 Bq) of a 60Co source. Hot samples can be automatically transferred from the cell to the sample chamber of the analyzer. Contamination inside the equipment through sputtering of the radioactive materials can be reduced with a special device. Distribution and migration of fission products, such as 137Cs, 138Ba, and 90Sr, and of fissile materials, such as 235U and 239Pu in irradiated mixed-oxide fuel, and isotopic ratios of the elements can be obtained very precisely and quickly.