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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
Trio of GAIN vouchers for sensors, materials, and fuels testing
The Department of Energy announced on June 5 that three companies—all of which are new to the Gateway for Accelerated Innovation in Nuclear (GAIN) voucher program—will receive vouchers to support their research on advanced fuels, materials, and sensors. The second round fiscal year 2025 vouchers will let the companies access specialized research facilities and expertise in the DOE’s national laboratory complex.
Byung-Ho Lee, Yang-Hyun Koo, Han-Soo Kim, Jae-Yong Oh, Young-Woo Lee, Dong-Seong Sohn, Wolfgang Wiesenack
Nuclear Technology | Volume 172 | Number 3 | December 2010 | Pages 246-254
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT10-A10933
Articles are hosted by Taylor and Francis Online.
Attrition-milling technology for fabricating mixed oxide (MOX) fuel was developed to mix the plutonium in UO2 fuels as homogeneously as possible. The fabricated MOX fuels were instrumented with temperature and pressure gauges that enabled one to measure the fuel temperature and rod internal pressure online. An irradiation test in the Halden reactor was performed to investigate the in-pile behavior of the fabricated MOX fuel. The irradiation of 1020 effective full-power days was successfully accomplished with good integrity of the test fuel rods. The rod average burnup reached [approximately]50 MWd/kg HM, and the measured fuel centerline temperature was [approximately]1000°C for the MOX fuels. A significant fission gas release was observed due to the high power level. The online measured in-pile performance data of the two attrition-milled MOX fuel rods were analyzed and compared with the fuel performance code COSMOS. COSMOS simulated the fuel centerline temperature and rod internal pressure for both MOX fuel rods. The analysis by COSMOS showed good agreement with the online measured in-pile behavior of MOX fuel.
