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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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Fusion Science and Technology
Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Ion Cristescu, A. Bükki-Deme, R. Carr, N. Gramlich, R. Groessle, C. Melzer, P. Schaefer, Stefan Welte
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 225-230
Technical Paper | doi.org/10.1080/15361055.2017.1288057
Articles are hosted by Taylor and Francis Online.
The design of ITER tritium processing systems will benefit from experimental data and process validation based on experimental facilities that are ITER scale relevant. Several rigs and experimental facilities have been enhanced and developed at the Tritium Laboratory Karlsruhe (TLK) in order to explore a wide range of envisaged scenarios of tritium plant systems, such as the Water Detritiation System (WDS), Isotope Separation System (ISS) and highly tritiated water processing. In the last few years, detailed experimental investigations and process modeling have been conducted in relation to the Combined Electrolysis Catalytic Exchange and Isotope Separation (CECE-ISS) systems which were focused on evaluation of the impact of deuterium build-up and accumulation in the CECE system. An enhanced configuration of the ITER WDS has been developed, that allows mitigation of the effects due to deuterium accumulation and reduction of the tritium inventory within the electrolysis system. In addition, the benefits concerning the interface between the WDS and ISS are presented. Significant efforts have been made to enhance the simulation tool TRIMO++ that was calibrated against the experimental results collected from the experimental rigs. The new features of the simulation tools are introduced as well.
The main references of a new method aiming to mitigate the tritium permeation from the tritium processes streams into the non-contaminated streams such as steam generators are introduced. The reference configuration of first phase of the experimental rigs and the preliminary experimental activities are presented as well.