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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.
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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
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
Tae-Hoon Lee, Young-Soo Kim, Tae-Je Kwon, Hee-Sung Shin, Ho-Dong Kim
Nuclear Technology | Volume 179 | Number 2 | August 2012 | Pages 196-204
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT11-77
Articles are hosted by Taylor and Francis Online.
In pyroprocessing it is important to determine the amount of Pu in the various streams of materials involved. This paper presents two approaches to determine the Pu mass of spent fuel assemblies using nondestructive assay and burnup simulation code. Cm balance is adopted and the concept of "Cm ratio," the mass ratio of Pu to Cm, is used for the nuclear material accountancy for the model pyroprocessing facility. The biggest error of the nuclear material accountancy is expected to arise from the determination of Pu mass and Cm ratio in input homogeneously mixed uranium oxide powder, which is assayed nondestructively. One approach to determine the Pu mass and Cm ratio is to apply the average burnup of spent fuel and determine the Pu mass and Cm ratio by using the ORIGEN code. The estimated error in Pu mass determined by this method ranges from 0.94% to 2.33% for a total of 225 spent fuel assemblies of various burnup, initial enrichment, and cooling time. The other approach is to use the functional relationship between the neutron emission rate and Pu mass of spent fuel. The error in Pu mass calculated using this method ranges from -1.68% to 3.86%.