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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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
NRC updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
Byung-Ho Lee, Yang-Hyun Koo, Je-Yong Oh, Jin-Sik Cheon, Dong-Seong Sohn
Nuclear Technology | Volume 157 | Number 1 | January 2007 | Pages 53-64
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3801
Articles are hosted by Taylor and Francis Online.
A fuel performance code, COSMOS, was developed for an analysis of the thermal behavior and fission gas release of both mixed-oxide (MOX) and UO2 fuels up to high burnup. The models have been improved for the fuel thermal conductivity, the fission gas release, and the cladding corrosion and creep. In particular, the thermal conductivity and fission gas release models were restructured with due consideration for the inhomogeneity of the MOX fuel. These improvements enhanced COSMOS's precision for predicting the in-pile behavior of the MOX fuel. The COSMOS code also extends its applicability to the sophisticatedly instrumented fuel test in a research reactor. With the improved models, the recent in-pile test results were analyzed and compared with the code's prediction. The database consists of the instrumented MOX fuel test in a research reactor, the postirradiation examination results after an irradiation in a commercial reactor, and a preliminary instrumented test in the HANARO reactor. With the rigorously characterized fabrication data and irradiation information, the COSMOS code predicted the in-pile behaviors well, such as the fuel temperature, rod internal pressure, fission gas release, and cladding properties of MOX and UO2 fuels. The estimations by COSMOS also demonstrated its applicability to the instrumented irradiation test.
