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Proceedings Papers

Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC

Shichang Liu, Zhenyu Wang, Rui Che
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A027, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134661
https://doi.org/10.1115/ICONE31-134661
View Paper titled, Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC
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Topics: Fusion reactors, Radiation (Physics), Algorithms, Resolution (Optics), Accuracy and precision, Computational methods, Geometry, Nuclear design, Particulate matter, Safety
Proceedings Papers

Application of Virtual Reality Technology in Human Factors Verification of Nuclear Power Plant Design

Dong Hao, YanFang Fan, BingHe Bai
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A064, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136054
https://doi.org/10.1115/ICONE31-136054
View Paper titled, Application of Virtual Reality Technology in Human Factors Verification of Nuclear Power Plant Design
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Topics: Ergonomics, Human factors, Nuclear design, Virtual reality
Proceedings Papers

Verification of the RMC-SaraGR Nuclear Design Code System Based on the HTTR Benchmark

Yuan Yuan, Guoming Liu, Peng Zhang
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135368
https://doi.org/10.1115/ICONE31-135368
View Paper titled, Verification of the RMC-SaraGR Nuclear Design Code System Based on the HTTR Benchmark
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Topics: Neutrons, Nuclear design, Uncertainty, Very high temperature reactors, Cross section (Physics), Fuels, Modeling, Rods
Proceedings Papers

A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core

Jie Liu, Chunyu Zhang, Zhihao Zheng, Jiesheng Min
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A073, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93008
https://doi.org/10.1115/ICONE29-93008
View Paper titled, A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core
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Topics: Fluid dynamics, Physics, Simulation, Computational fluid dynamics, Structural analysis, American Petroleum Institute, Computation, Computer simulation, Computer software, Computer-aided engineering
Proceedings Papers

3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

Qing Yang, Jianhua Xia, Xiaojing Liu, Qingquan Pan, Hui He, Tengfei Zhang
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A038, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-94534
https://doi.org/10.1115/ICONE29-94534
View Paper titled, 3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core
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Topics: Physics, Neutrons, Simulation, Computational fluid dynamics, Computer simulation, Conceptual design, Coolants, Design, Nuclear design, Optimization
Proceedings Papers

The Applicability Analysis of Fusion Reactors and China Nuclear Safety Code HAF102

Yijie Qian, Chong Li
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A026, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91692
https://doi.org/10.1115/ICONE29-91692
View Paper titled, The Applicability Analysis of Fusion Reactors and China Nuclear Safety Code HAF102
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Topics: China, Fusion reactors, Safety, Design, Defense industry, Nuclear design, Nuclear fission, Nuclear fusion, Nuclear reactors, Regulations
Proceedings Papers

Nuclear Power Plant Design Optimization Based on Risk-Informed Method

Wenjing Li, Yu Liu, Gaopeng Wang, Xinli Yu
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89268
https://doi.org/10.1115/ICONE29-89268
View Paper titled, Nuclear Power Plant Design Optimization Based on Risk-Informed Method
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Topics: Nuclear design, Optimization, Risk, Design, Nuclear power stations, Accidents, Cavities, Vessels, China, Damage
Proceedings Papers

The Core Design Modifications for Stirling Thermal-Electric Integrated Micro Reactor

Xia Yan, Xuedong Ou, Mingqiang Lin, Jian Mou, Shaolei Sun, Chunyun Chi, Chunqing Zhao, Qin Zhou
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A045, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93465
https://doi.org/10.1115/ICONE29-93465
View Paper titled, The Core Design Modifications for Stirling Thermal-Electric Integrated Micro Reactor
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Topics: Design, Fuels, Compression, Coolants, Flow (Dynamics), Generators, Gravity (Force), Heat, Heat transfer, Nuclear design
Proceedings Papers

Application of ALARP Concept in Nuclear Power Plant Design — A Case Study in HPR1000

Dongyuan Li, Shi Qing, Haiying Luo, Jinkai Wang, Jiaoshen Xu
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92241
https://doi.org/10.1115/ICONE29-92241
View Paper titled, Application of ALARP Concept in Nuclear Power Plant Design — A Case Study in HPR1000
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Topics: Design, Nuclear design, Risk, Licensing, Safety, Economics , Nuclear power stations, Plant design, Regulations, Self-evaluation
Proceedings Papers

Validation of TULIP via ICSBEP Critical Benchmark

Wenjie Chen, Xianan Du, Youqi Zheng, Yongping Wang, Rong Wang, Hongchun Wu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A113, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93353
https://doi.org/10.1115/ICONE29-93353
View Paper titled, Validation of TULIP via ICSBEP Critical Benchmark
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Topics: Computational physics, Cross section (Physics), Design, Doppler effect, Feedback, Manufacturing, Neutrons, Nuclear design, Nuclear engineering, Nuclear fission
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64525
https://doi.org/10.1115/ICONE28-64525
View Paper titled, ARKADIA – for the Innovation of Advanced Nuclear Reactor Design
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Topics: Artificial intelligence, Computer simulation, Innovation, Nuclear design, Nuclear reactors, Optimization, Design, Safety, Carbon, Coolants
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81090
https://doi.org/10.1115/ICONE26-81090
View Paper titled, Modelling and Simulation Activities in Support of the UK Nuclear R&D Programme on Digital Reactor Design
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Topics: Design, Modeling, Simulation, Pressurized water reactors, Physics, Bricks, Graphite, Nuclear design
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82244
https://doi.org/10.1115/ICONE26-82244
View Paper titled, Criticality Safety Issues in Nuclear Design of HP-SMTCs Space Reactor
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Topics: Nuclear design, Safety, Accidents, Risk, Seawater, Absorption, Design, Heat, Neutrons, Nuclear power
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81544
https://doi.org/10.1115/ICONE26-81544
View Paper titled, Study on the Prediction of DNB-Type Critical Heat Flux in Rod Bundle Under Motion Conditions
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Topics: Critical heat flux, Fuel rods, Flow (Dynamics), Fuels, Vapors, Bubbles, Coolants, Cross-flow, Damage, Failure
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82325
https://doi.org/10.1115/ICONE26-82325
View Paper titled, A Brief Review of Computational Intelligence Techniques for Critical Heat Flux Prediction
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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

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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81441
https://doi.org/10.1115/ICONE26-81441
View Paper titled, Uncertainty Analysis of Power Distribution for NESTOR Based on the Double Latin Hypercube Sampling Method
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Topics: Sampling methods, Uncertainty analysis, Uncertainty, Nuclear design, Computer software, Approximation, Computation, Design, Economics , Modeling
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66441
https://doi.org/10.1115/ICONE25-66441
View Paper titled, An Image-Based Micro-Scale Fracture Model for Weld Zone in Nuclear Pipe and Component
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66346
https://doi.org/10.1115/ICONE25-66346
View Paper titled, Nuclear Island Basemat Modeling for Generation III Nuclear Power Plant Design in China
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66045
https://doi.org/10.1115/ICONE25-66045
View Paper titled, A Novel Method for Solving Reactor Physics Diffusion and Transport Equation
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66573
https://doi.org/10.1115/ICONE25-66573
View Paper titled, Development and Verification of the PWR Lattice Code PANDA
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Topics: Pressurized water reactors, Collapse, Cross section (Physics), Design, Nuclear design, Nuclear engineering, Physics, Resonance