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Proceedings Papers

ARKADIA – for the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Takashi Takata, Yasuhiro Enuma
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A007, August 4–6, 2021
Paper No: ICONE28-64525
DOI: https://doi.org/10.1115/ICONE28-64525
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Topics: Artificial intelligence, Computer simulation, Innovation, Nuclear design, Nuclear reactors, Optimization, Design, Safety, Carbon, Coolants
Proceedings Papers

Uncertainty Analysis of Power Distribution for NESTOR Based on the Double Latin Hypercube Sampling Method

Hongkuan Liao, Qing Li, Yingrui Yu, Yuying Hu, Lei Wu, Chenlin Wang, Jinyu Wang, Jinghui Wang, Peng Xiao
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A008, July 22–26, 2018
Paper No: ICONE26-81441
DOI: https://doi.org/10.1115/ICONE26-81441
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Topics: Sampling methods, Uncertainty analysis, Uncertainty, Nuclear design, Computer software, Approximation, Computation, Design, Economics , Modeling
Proceedings Papers

Criticality Safety Issues in Nuclear Design of HP-SMTCs Space Reactor

Songyang Li, Dingqu Wang, Yueyuan Jiang, Weihua Li, Wenli Guo
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A047, July 22–26, 2018
Paper No: ICONE26-82244
DOI: https://doi.org/10.1115/ICONE26-82244
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Topics: Nuclear design, Safety, Accidents, Risk, Seawater, Absorption, Design, Heat, Neutrons, Nuclear power
Proceedings Papers

A Brief Review of Computational Intelligence Techniques for Critical Heat Flux Prediction

B. T. Jiang, Y. N. Liu
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A050, July 22–26, 2018
Paper No: ICONE26-82325
DOI: https://doi.org/10.1115/ICONE26-82325
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Topics: Critical heat flux, Design, Nuclear reactors, Artificial neural networks, Fuel rods, Nuclear power stations, Safety, Temperature, Water, Economics
Proceedings Papers

Modelling and Simulation Activities in Support of the UK Nuclear R&D Programme on Digital Reactor Design

B. Lindley, D. Allen, J. Lillington, A. Smethurst, P. Smith, D. Bowman, L. Dwyer, K. Lai, A. Levers, K. Vikhorev, D. Litskevich, B. Merk, E. Patelli, E. Patterson, M. Bankhead, A. Peakman, S. de Haas, C. Jackson, J. Draup, E. Galenne, G. Parks, E. Shwageraus, M. D. Eaton
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A004, July 22–26, 2018
Paper No: ICONE26-81090
DOI: https://doi.org/10.1115/ICONE26-81090
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Topics: Design, Modeling, Simulation, Pressurized water reactors, Physics, Bricks, Graphite, Nuclear design
Proceedings Papers

Study on the Prediction of DNB-Type Critical Heat Flux in Rod Bundle Under Motion Conditions

Siyang Huang, Xiaoyan Wang, Wenxi Tian, Ronghua Chen, Junmei Wu, G. H. Su, Suizheng Qiu
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A050, July 22–26, 2018
Paper No: ICONE26-81544
DOI: https://doi.org/10.1115/ICONE26-81544
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Topics: Critical heat flux, Fuel rods, Flow (Dynamics), Fuels, Vapors, Bubbles, Coolants, Cross-flow, Damage, Failure
Proceedings Papers

Performance and Application of Internal Flood Probabilistic Safety Assessment in Nuclear Power Plant Design

Lihua Huang, Xiang Liu, Lijuan Wang
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T14A014, July 2–6, 2017
Paper No: ICONE25-66398
DOI: https://doi.org/10.1115/ICONE25-66398
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Topics: Floods, Nuclear design, Probabilistic safety assessment, Nuclear power stations, Design, Risk
Proceedings Papers

An Image-Based Micro-Scale Fracture Model for Weld Zone in Nuclear Pipe and Component

Xiaoming Bai, Liangang Zheng, Xinjun Wang, Xi Lv
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A047, July 2–6, 2017
Paper No: ICONE25-66441
DOI: https://doi.org/10.1115/ICONE25-66441
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Topics: Fracture (Materials), Fracture (Process), Microscale devices, Pipes, Finite element analysis, Boundary-value problems, Damping, Engineering standards, Materials properties, Mechanical properties
Proceedings Papers

Nuclear Island Basemat Modeling for Generation III Nuclear Power Plant Design in China

Ziduan Shang, Chunhua Wu, Boyu Han, Chenyu Chang, Lutong Zhang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A038, July 2–6, 2017
Paper No: ICONE25-66346
DOI: https://doi.org/10.1115/ICONE25-66346
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Topics: China, Modeling, Nuclear design, Soil, Stress, Design, Concretes, Safety, Containment vessels, Dimensions
Proceedings Papers

A Novel Method for Solving Reactor Physics Diffusion and Transport Equation

Hu Wenjun, Cao Yonggang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A002, July 2–6, 2017
Paper No: ICONE25-66045
DOI: https://doi.org/10.1115/ICONE25-66045
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Topics: Diffusion (Physics), Physics, Boundary-value problems, Computer software, Nuclear design, Numerical analysis
Proceedings Papers

Development and Verification of the PWR Lattice Code PANDA

Hongbo Zhang, Chuntao Tang, Weiyan Yang, Guangwen Bi, Bo Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A018, July 2–6, 2017
Paper No: ICONE25-66573
DOI: https://doi.org/10.1115/ICONE25-66573
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Topics: Pressurized water reactors, Collapse, Cross section (Physics), Design, Nuclear design, Nuclear engineering, Physics, Resonance
Proceedings Papers

Development of NPP Collaborative Design Management Platform

Shen Jun, Li Xiaoyan, Wang Yong
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T13A003, July 2–6, 2017
Paper No: ICONE25-66105
DOI: https://doi.org/10.1115/ICONE25-66105
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Topics: Design, Nuclear power stations, Construction, Nuclear design, Optimization
Proceedings Papers

Application of GIS in the General Layout of a Nuclear Power Plant

Peng Fu, Ming Wang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T13A012, July 2–6, 2017
Paper No: ICONE25-67164
DOI: https://doi.org/10.1115/ICONE25-67164
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Topics: Nuclear power stations, Design, Databases, Nuclear construction, Nuclear design, Optimization, Safety, Three-dimensional modeling
Proceedings Papers

Development and Application of Cobalt Adjuster Rod for 60 Co Medical Radioactive Sources Production in CANDU-6 Reactor

Jie Ding, Yu Dang, Libing Zhu, Chuntao Tang, Hui Li, Huimin Qin
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A022, July 2–6, 2017
Paper No: ICONE25-66623
DOI: https://doi.org/10.1115/ICONE25-66623
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Topics: Biomedicine, Cobalt, Design, Safety, Manufacturing, Nuclear design
Proceedings Papers

Research and Engineering Application of Repaired Fuel Assembly Reusing Technique

Lihua Wang, Qingxiang Yang, Ping Yang, Jiazheng Liu, Libing Zhu, Bo Yang, Hong Cao, Zhe Wang, Yang Ding, Jie Ding
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A024, July 2–6, 2017
Paper No: ICONE25-66659
DOI: https://doi.org/10.1115/ICONE25-66659
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Topics: Fuels, Manufacturing, Design, Fuel rods, Nuclear power stations, Economics , Rods, Safety, Computer software, Coolants
Proceedings Papers

Penetration Jet Impingement Calculation in Engineering Application

Tong Wu, Ying Zhou, Tao Qi
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A022, July 2–6, 2017
Paper No: ICONE25-67096
DOI: https://doi.org/10.1115/ICONE25-67096
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Topics: Drops, Engineering systems and industry applications, Enthalpy, Flashing, Floods, Flow (Dynamics), Fluids, Hazard analysis, Hot water, Jets
Proceedings Papers

The Effect on the Support Seismic Loads of Primary Equipment With Different Reactor Coolant Pump

Ye Xianhui, Cai Fengchun, Lan Bin, Zhang Yixiong
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T07A002, June 26–30, 2016
Paper No: ICONE24-60091
DOI: https://doi.org/10.1115/ICONE24-60091
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Topics: Nuclear reactor coolants, Pumps, Stress, Computational methods, Economics , Nuclear design, Safety, Seismic analysis
Proceedings Papers

Thermal Hydraulic Facility for Full Length Bundle CHF Experiment

Shengjie Qin, Xuemei Lang, Wenbin Zhuo, Pengzhou Li, Ye Liu
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A030, July 7–11, 2014
Paper No: ICONE22-30899
DOI: https://doi.org/10.1115/ICONE22-30899
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Topics: Critical heat flux, Fuel rods, Geometry, China, Cladding systems (Building), Failure, Fuels, Manufacturing, Nuclear design, Nuclear power
Proceedings Papers

Development of Grid Depression Model for GalaxyCosmo-S

Hiroki Koike, Kazuki Kirimura, Kazuya Yamaji, Shinya Kosaka, Hideki Matsumoto
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A006, July 7–11, 2014
Paper No: ICONE22-30379
DOI: https://doi.org/10.1115/ICONE22-30379
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Topics: Cycles, Design, Fittings, Fuels, Manufacturing, Nuclear design, Pressurized water reactors, Sensors, Uncertainty
Proceedings Papers

Pressure Drop Analysis of a Re-Entrant Fuel Channel in a Pressure-Channel Type SuperCritical Water-Cooled Reactor

S. Maghsoudi, W. Peiman, I. Pioro, K. Gabriel
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A045, July 7–11, 2014
Paper No: ICONE22-30616
DOI: https://doi.org/10.1115/ICONE22-30616
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Topics: Fuels, Pressure, Pressure drop, Water, Friction, Gravity (Force), Nuclear design, Steady state, Supercritical water reactors, Temperature profiles