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2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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India’s PFBR attains criticality at last
Prime Minister Narendra Modi proclaimed it “a proud moment for India” when on April 6 the 500-MWe, sodium-cooled Prototype Fast Breeder Reactor (PFBR) achieved initial criticality. This milestone, which comes some 22 years after the continually delayed PFBR project began, marks India’s entrance into the second stage of its three-stage nuclear program, which has the ultimate goal of supporting the country’s nuclear power program with its significant thorium reserves.
Technical Session|Sponsored by NISD
Tuesday, November 17, 2020|4:50–6:30PM EST
Session Chair:
Matthew Bucknor (ANL)
Alternate Chair:
David S. Grabaskas
Session Organizer:
Andrew J. Clark
Staff Producer:
Julie Bry (American Nuclear Society)
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Safety Analysis of the Conceptual Versatile Test Reactor Design
Tyler S. Sumner (Argonne National Laboratory), T. H. Fanning (Argonne National Laboratory), J. W. Thomas (Argonne National Laboratory)
Paper
Impact of the Control Rod Withdrawal Rate during Power Ascension Operations
Justin W. Thomas (Argonne National Laboratory), Tyler S. Sumner (Argonne National Laboratory), Thomas H. Fanning (Argonne National Laboratory)
Versatile Test Reactor Pump Coastown Assessment
Tyler S. Sumner (Argonne National Laboratory), T. H. Fanning (Argonne National Laboratory)
Initial Sensitivity Analyses for Versatile Test Reactor Transient Safety Performance
Justin W. Thomas (Argonne National Laboratory), Lander Ibarra (Argonne National Laboratory), Tyler S. Sumner (Argonne National Laboratory)
Analysis of Versatile Test Reactor Pump Overcooling Transients
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