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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Nicholas Tsoulfanidis—ANS member since 1969
We welcome ANS members who have careered in the community to submit their own Nuclear Legacy stories, so that the personal history of nuclear power can be captured. For information on submitting your stories, contact nucnews@ans.org.
As an undergraduate I studied physics at the University of Athens. I entered the university in 1955 after successfully passing a national exam (came up fourth in a field of about 700 candidates). Upon graduation and finishing my mandatory two-year military service, the plan was to teach physics either in a public high school or as a tutor for a private for-profit institution, preparing high school students for the national exam.
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.