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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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Latest News
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 THD
Wednesday, November 18, 2020|12:00–2:10PM EST
Session Chair:
Jun Wang
Session Organizer:
Alternate Chair:
John C. Luxat
Staff Producer:
Janet Davis (American Nuclear Society)
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Coupling of OpenFOAM Stress Analysis Solver and ANLHTP for Thermo-Mechanical Analysis of a Heat Pipe Cooled Micro Reactor Core
Myung Jin Jeong (Seoul National University), Changho Lee (Argonne National Laboratory), Yeon Sang Jung (Argonne National Laboratory), Hyoung Kyu Cho (Seoul National University), San Lee (Seoul National University)
Paper
Presentation Video (Visible to Attendees) — 1080p
Presentation Video (Visible to Attendees) — 720p
Preliminary Fuel Performance and Thermal Hydraulic Modeling of the MPCMIV Benchmark
Tomasz Kozlowski (University of Illinois), Travis C. Mui (University of Illinois Urbana Champaign)
Coupled Multiphysics Simulation of Pool-Type Molten Salt Reactors Using Griffin/Pronghorn
Andrew Hermosillo (TAMU), Nicolas P. Martin (Idaho National Laboratory), Yaqi Wang (Idaho National Laboratory), Sebastian Schunert (Idaho National Laboratory), Abdalla Abou-Jaoude (INL), Paolo Balestra (INL)
Multiphysics Modeling of an Annular Linear Induction Pump
Jacob Eapen (North Carolina State University), Steven Shannon (North Carolina State University), Anant Raj (North Carolina State University), Mohammed K. Shutayfi (North Carolina State University)
Anubis: A Neutronics-Thermal Hydraulics Coupling Platform for Flow Accelerated Corrosion Modeling in Reactor Conditions
Cetin Unal (Los Alamos National Laboratory), Osman Anderoglu (University of New Mexico), Khaled Talaat (University of New Mexico)
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