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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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.
S.K. Sood, C. Fong, K.M. Kalyanam, K.B. Woodall, A. Busigin
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 742-747
Tritium Processing | Proceedings of the Fifth Topical Meeting on Tritium Technology in Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30493
Articles are hosted by Taylor and Francis Online.
The High Temperature Isotopic Exchange (HITEX) process has been proposed as a simple and reliable option for detritiating impurities in the ITER plasma exhaust.1 The process relies on the well known principle of catalytic equilibration, does not involve complicated decomposition reactions, and avoids the formation of tritiated water. The original HITEX process was conceived as a simple batch system which could yield extremely high detritiation factors (∼ 109). However, batch operation (for an ITER scale/impurity feed compositions) necessitates the holdup of tritium inventory (101 gT) equivalent to one batch in the HITEX feed tank. This paper compares batch and once-through HITEX options in light of calculated and experimental results. Tritium inventories, hydrogen swamping rates and Decontamination Factors (DF's) are compared with the objective of optimizing the process configuration for ITER. A promising HITEX configuration for ITER is composed of a once-through first stage which removes the bulk of the tritium in the impurities, followed by a batch-wise second stage which provides a large decontamination factor. Such a hybrid arrangement promises to produce the required DF of 600,000 with a tritium inventory of < 5 g and a hydrogen swamping ratio of about 26:1. The hybrid arrangement is expected to be robust, since it can be built using industrially proven components.