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Proceedings Papers

New Exploration on TMSR: The Lattice Optimization

Shengyi Si, Qichang Chen, Hua Bei, Jinkun Zhao
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A010, July 7–11, 2014
Paper No: ICONE22-30220
DOI: https://doi.org/10.1115/ICONE22-30220
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Topics: Computers, Fuels, Molten salt reactors, Optimization, Safety, Sustainability, Tradeoffs
Proceedings Papers

Nuclear-Coupled Thermal Hydraulics Stability of a Natural Circulation Lead-Cooled Fast Reactor

Qiyue Lu, Rizwan Uddin
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A028, July 7–11, 2014
Paper No: ICONE22-31070
DOI: https://doi.org/10.1115/ICONE22-31070
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Topics: Fast neutron reactors, Stability, Thermal hydraulics, Design, Feedback, Flow (Dynamics), Simulation
Proceedings Papers

COUPLE, A Time-Dependent Coupled Neutronics and Thermal-Hydraulics Code, and its Application to MSFR

Dalin Zhang, Zhi-Gang Zhai, Andrei Rineiski, Zhangpeng Guo, Chenglong Wang, Yao Xiao, Suizheng Qiu
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A019, July 7–11, 2014
Paper No: ICONE22-30609
DOI: https://doi.org/10.1115/ICONE22-30609
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Topics: Thermal hydraulics, Fuels, Neutrons, Flow (Dynamics), Flux (Metallurgy), Molten salt reactors, Temperature, Vortices, Fast neutron reactors, Numerical analysis
Proceedings Papers

Coupled Three Dimensional Neutronics/Thermal-Hydraulics Code STTA for SCWR Core Transient Analysis

Lianjie Wang, Wenbo Zhao, Ping Yang, Bingde Chen, Dong Yao
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A001, July 7–11, 2014
Paper No: ICONE22-30078
DOI: https://doi.org/10.1115/ICONE22-30078
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Topics: Supercritical water reactors, Thermal hydraulics, Transient analysis, Pressure, Pressurized water reactors, Transients (Dynamics), Accidents, Boundary-value problems, Diffusion (Physics), Green's function methods
Proceedings Papers

The iBR: A Generation III.7 Reactor After the Fukushima Daiichi Accident

Takashi Sato, Keiji Matsumoto, Toshikazu Kurosaki, Mitsuhiro Maida
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A011, July 7–11, 2014
Paper No: ICONE22-30309
DOI: https://doi.org/10.1115/ICONE22-30309
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Safety, Containment, Design, Aircraft, Construction, Domes (Structural elements), Boiling water reactors, Composite materials
Proceedings Papers

Microstructure and Mechanical Properties of 9Cr1Mo Steel-12Cr2Si Steel Bimetallic Billet Produced by Centrifugal Casting

Gidong Kim, Hong Ki Kim, Woosung Kim, Namkyu Kim, Sanghoon Lee, Sangwoo Song, Youngho Son
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A029, July 7–11, 2014
Paper No: ICONE22-31076
DOI: https://doi.org/10.1115/ICONE22-31076
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Topics: Casting, Mechanical properties, Steel, Corrosion resistance, High temperature, ASME Standards, Coolants, Fast neutron reactors, Ferrites (Magnetic materials), Heat treating (Metalworking)
Proceedings Papers

Design of 500 MWe Metal Fuel Demonstration Fast Reactor

Chellapandi Perumal, V. Balasubramaniyan, P. Puthiyavinayagam, Raghupathy Sundararajan, Madhusoodanan Kanakkil, P. Selvaraj, P. R. Vasudeva Rao
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A020, July 7–11, 2014
Paper No: ICONE22-30727
DOI: https://doi.org/10.1115/ICONE22-30727
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Topics: Design, Fast neutron reactors, Fuels, Metals, Breeder reactors, Heavy water reactors, Uranium, Nuclear power, Construction, Engineering prototypes
Proceedings Papers

A Design of Magnetic Load Simulator for the Rotor Dropping Protection Experiment System of Helium Circulator in HTR

Zhu Liang, Wang Hong
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A002, July 7–11, 2014
Paper No: ICONE22-30080
DOI: https://doi.org/10.1115/ICONE22-30080
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Topics: Design, Helium, Rotors, Stress, Bearings, Magnetic bearings, Clearances (Engineering), Damage, Electromagnetic force, Engines
Proceedings Papers

Design Improvement Studies for Future SFR

Rajan Babu V., V. Balasubramaniyan, Raghupathy Sundararajan, P. Puthiyavinayagam, Chellapandi Perumal
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A021, July 7–11, 2014
Paper No: ICONE22-30742
DOI: https://doi.org/10.1115/ICONE22-30742
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Topics: Design, Sodium fast reactors, Manufacturing, Sodium, Construction, Heat, Vessels, Breeder reactors, Circuits, Dimensions
Proceedings Papers

Safety Analyses for Pb-Bi-Cooled Direct Contact Boiling Water Fast Reactor (PBWFR)

Yonghong Tian, Wenxi Tian, Dalin Zhang, Guanghui Su, Suizheng Qiu
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A012, July 7–11, 2014
Paper No: ICONE22-30318
DOI: https://doi.org/10.1115/ICONE22-30318
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Topics: Boiling, Fast neutron reactors, Safety, Water, Steam, Accidents, Pumps, Boilers, Bubbles, Buoyancy
Proceedings Papers

Lead Fast Reactor Sustainability

Marco Ciotti, Jorge L. Manzano, Giacomo Grasso, Luigi Mansani, Carlo Petrovich
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A030, July 7–11, 2014
Paper No: ICONE22-31092
DOI: https://doi.org/10.1115/ICONE22-31092
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Topics: Fast neutron reactors, Sustainability, Carbon dioxide, Nuclear fission, Nuclear fuel cycle, Safety, Absorption, Batteries, Carbon, Chemical potential
Proceedings Papers

Progress of the HTR-10 Measured Data Utilization

Fubing Chen, Yujie Dong, Yanhua Zheng, Lei Shi, Fu Li, Zuoyi Zhang
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A003, July 7–11, 2014
Paper No: ICONE22-30088
DOI: https://doi.org/10.1115/ICONE22-30088
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Topics: China, Computer software, Design, High temperature, Safety, Testing, Very high temperature reactors
Proceedings Papers

HELENA: A Heavy Liquid Metal Multi-Purpose Loop for Thermal-Hydraulics, Corrosion and Component Test

I. Di Piazza, M. Tarantino, P. Agostini, P. Gaggini
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A022, July 7–11, 2014
Paper No: ICONE22-30784
DOI: https://doi.org/10.1115/ICONE22-30784
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Topics: Corrosion, Liquid metals, Thermal hydraulics, Pumps, Flow (Dynamics), High temperature, Oxygen, Pressure, Shells, Water
Proceedings Papers

Transient Analysis of Crossduct Break Scenarios Using the CATHARE2 Code for the 75MW ALLEGRO Demonstrator

Gusztáv Mayer, Fabrice Bentivoglio
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A031, July 7–11, 2014
Paper No: ICONE22-31094
DOI: https://doi.org/10.1115/ICONE22-31094
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Topics: Cladding systems (Building), Collaboration, Design, Fast neutron reactors, Helium, Melting point, Modeling, Nitrogen, Pipes, Roads
Proceedings Papers

Assessment of the Effects of Anisotropy in TRIGA Based on 3D-AGENT Methodology

Hermilo Hernandez, Tatjana Jevremovic
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A004, July 7–11, 2014
Paper No: ICONE22-30138
DOI: https://doi.org/10.1115/ICONE22-30138
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Topics: Anisotropy, Electromagnetic scattering, Radiation scattering, Scattering (Physics), Approximation, Geometry, Modeling, Neutron diffraction, Neutrons, Testing
Proceedings Papers

Safety Feature of EU-ABWR for Fukushima Accident

Kazuhiro Kamei, Masatomo Kuroda, Yoshihiro Kojima, Kazuki Yano
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A013, July 7–11, 2014
Paper No: ICONE22-30332
DOI: https://doi.org/10.1115/ICONE22-30332
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Topics: Fukushima nuclear disaster, Japan, 2011, Safety, Design, Accidents, Aircraft, Boiling water reactors, Containment, Defense industry
Proceedings Papers

Design of Experimental Loop With Supercritical Carbon Dioxide

Ladislav Vesely, Vaclav Dostal, Petr Hajek
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A023, July 7–11, 2014
Paper No: ICONE22-30798
DOI: https://doi.org/10.1115/ICONE22-30798
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Topics: Design, Supercritical carbon dioxide, Cycles, Collaboration, Construction, Heat transfer, Testing
Proceedings Papers

The ARCADIA Project in Support of the ALFRED Concept

Daniela Diaconu, Marin Constantin, Giacomo Grasso, Georgios Glinatsis, Fosca Di Gabriele, Alessandro Alemberti, Didier De Bruyn, Egidijus Urbonavicius
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A032, July 7–11, 2014
Paper No: ICONE22-31109
DOI: https://doi.org/10.1115/ICONE22-31109
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Topics: Safety, Sustainability
Proceedings Papers

Preliminary Core Design of the Long Life S-CO 2 Cooled Fast Reactor With 300WMth

Baolin Liu, Hongchun Wu, Youqi Zheng, Liangzhi Cao, Xianbao Yuan
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A014, July 7–11, 2014
Paper No: ICONE22-30390
DOI: https://doi.org/10.1115/ICONE22-30390
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Topics: Design, Fast neutron reactors, Supercritical carbon dioxide, Fuels, Ducts, Hydraulic couplings, Manufacturing, Neutrons, Nuclear power stations, Temperature
Proceedings Papers

Flowsheet Study of a Multistage Flash Desalination System for Cogeneration With High Temperature Gas-Cooled Reactor

Yu Kamiji, Hiroki Noguchi, Atsuhiko Terada, Xing Yan
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A005, July 7–11, 2014
Paper No: ICONE22-30142
DOI: https://doi.org/10.1115/ICONE22-30142
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Topics: Combined heat and power, Very high temperature reactors, Water, Heat, Waste heat, Heat recovery, Cycles, Energy generation, Gas turbines, Heat transfer