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Second round of Launch Pad selections includes eight newcomers
The National Reactor Innovation Center at Idaho National Laboratory has announced 13 project selections across 12 companies for the Nuclear Energy Launch Pad, a Department of Energy–led program that integrates reactor and fuel facility authorization, testing, and deployment support for private nuclear developers.
The Launch Pad emerged from the Reactor Pilot Program and Fuel Line Pilot Program.
According to INL, projects selected include reactor development and nuclear fuel cycle advancements, including fabrication, enrichment, and conversion technologies.
H. A. Boniface, N. V. Gnanapragasam, D. K. Ryland, S. Suppiah, A. Perevezentsev
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 241-245
Technical Paper | doi.org/10.1080/15361055.2017.1290970
Articles are hosted by Taylor and Francis Online.
The Water Detritiation System (WDS) designed for ITER is based on the combined electrolysis and catalytic exchange(CECE) process to ensure the emission of tritium to the environment is maintained below very strict limits. The CECE process is one of the processes for tritium removal that CNL (Canadian Nuclear Laboratories, formerly Atomic Energy of Canada Ltd.) has studied, developed and successfully demonstrated. In this work, CNL evaluated ITER’s design conditions of the exchange column and the electrolyser – the two key components of the CECE process (and the ITER WDS system) – to assess the effectiveness of tritium removal and investigate options to improve it. The evaluation was done using CNL’s CECE process simulation according to a protocol set out by ITER. Initially, calibration (benchmarking) of CNL’s hydrogen-water exchange column model was performed with a standard data set for a specified column to determine modeling parameters that resulted in a good match with the tritium concentration data. The model was then applied (with the same parameters) to the current WDS design. Some optimized conditions for the CECE process that could improve performance of the WDS to meet its design criteria were determined. The details of some of these assessments are presented here with particular attention to the WDS case where the feed water contains high levels of deuterium.