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Proceedings Papers

Verification and Validation of JMCT Monte Carlo Code in CPR1000

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Yaoxin Ye, Jun Zhao, Pengfei Bao
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93545
https://doi.org/10.1115/ICONE29-93545
View Paper titled, Verification and Validation of JMCT Monte Carlo Code in CPR1000
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Topics: China, Computer technology, Design, Fluence (Radiation measurement), Irradiation (Radiation exposure), Monte Carlo methods, Neutrons, Nuclear engineering, Nuclear power stations, Particulate matter
Proceedings Papers

Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR

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Jian Li, Ding She, Lei Shi
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64154
https://doi.org/10.1115/ICONE28-64154
View Paper titled, Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR
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Topics: Failure, Fuels, Probability, Very high temperature reactors, Irradiation (Radiation exposure), Particulate matter, Stress, Materials properties, Temperature, Anisotropy
Proceedings Papers

Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions

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Leo A. Carrilho
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A015, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16872
https://doi.org/10.1115/ICONE2020-16872
View Paper titled, Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions
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Topics: Pressurized water reactors, Stress, Stress analysis (Engineering), Water, Cladding systems (Building), Finite element model, Fluence (Radiation measurement), Temperature, Thermal expansion, Coolants
Proceedings Papers

Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV

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Yupeng Cao, Yinbiao He, Yifeng Huang, Binxi Wang, Yan Yu, Hui Li, Hu Hui
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A003, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16261
https://doi.org/10.1115/ICONE2020-16261
View Paper titled, Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV
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Topics: Embrittlement, Irradiation (Radiation exposure), Metals, Forging, Mechanical properties, China, Damage, Design, Fluence (Radiation measurement), Fracture toughness
Proceedings Papers

Calculational-Experimental Monitoring of Radiation Damage Parameters on VVER Equipment and Their Application During Equipment Residual Life-Time Estimation

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Pavel Borodkin, Azamat Gazetdinov, Nikolay Khrennikov
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T01A009, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81708
https://doi.org/10.1115/ICONE26-81708
View Paper titled, Calculational-Experimental Monitoring of Radiation Damage Parameters on VVER Equipment and Their Application During Equipment Residual Life-Time Estimation
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Topics: Damage, Embrittlement, Fluence (Radiation measurement), Metals, Neutrons, Nuclear power stations, Radiation (Physics), Radiation damage, Reactor vessels, Reliability
Proceedings Papers

Application of a 3D Discrete Ordinates-Monte Carlo Coupling Method on CAP1400 Cavity Streaming Calculation

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Zheng Zheng, Hui Li, Mengqi Wang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A011, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66401
https://doi.org/10.1115/ICONE25-66401
View Paper titled, Application of a 3D Discrete Ordinates-Monte Carlo Coupling Method on CAP1400 Cavity Streaming Calculation
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Topics: Cavities, Fluence (Radiation measurement), Neutrons, Photons, Errors, Computation, Dimensions, Geometry, Modeling, Nuclear power stations
Proceedings Papers

Modeling and Thermal Calculation of Fuel Rod With SiC f /SiC Cladding for LWRs

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Shang Xinyuan, Zhang Shaoyang, Zhang Aimin
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A040, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67078
https://doi.org/10.1115/ICONE25-67078
View Paper titled, Modeling and Thermal Calculation of Fuel Rod With SiC f /SiC Cladding for LWRs
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Topics: Cladding systems (Building), Fuel rods, Light water reactors, Modeling, Fuels, Composite materials, Design, Fibers, Fluence (Radiation measurement), Neutrons
Proceedings Papers

The Preliminary Shielding Analysis of CAP1400 Based on JMCT-S Code

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Yan Zhou, Zheng Zheng, Qiliang Mei
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A007, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66429
https://doi.org/10.1115/ICONE25-66429
View Paper titled, The Preliminary Shielding Analysis of CAP1400 Based on JMCT-S Code
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Topics: Computational methods, Cycles, Design, Engineering simulation, Equilibrium (Physics), Errors, Fluence (Radiation measurement), Geometry, Modeling, Neutron sources
Proceedings Papers

Fission Products Distribution in TRISO Coated Fuel Particles Irradiated to 3.22 X 10 21 n/cm 2 Fast Fluence at 1092°C

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Haiming Wen, Isabella J. Van Rooyen, Connie M. Hill, Tammy L. Trowbridge, Ben D. Coryell
Proc. ASME. NUCLRF2015, ASME 2015 Nuclear Forum, V001T03A004, June 28–July 2, 2015
Publisher: American Society of Mechanical Engineers
Paper No: NUCLRF2015-49695
https://doi.org/10.1115/NUCLRF2015-49695
View Paper titled, Fission Products Distribution in TRISO Coated Fuel Particles Irradiated to 3.22 X 10 21 n/cm 2 Fast Fluence at 1092°C
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Topics: Fluence (Radiation measurement), Fuels, Nuclear fission, Particulate matter, Silicon, Transmission electron microscopy, Carbon, Coating processes, Coatings, Electrons
Proceedings Papers

Sensitivity Evaluation of the Daily Thermal Predictions of the AGR-2 Experiment in the Advanced Test Reactor

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Grant L. Hawkes, James W. Sterbentz, Binh T. Pham
Proc. ASME. NUCLRF2015, ASME 2015 Nuclear Forum, V001T04A002, June 28–July 2, 2015
Publisher: American Society of Mechanical Engineers
Paper No: NUCLRF2015-49698
https://doi.org/10.1115/NUCLRF2015-49698
View Paper titled, Sensitivity Evaluation of the Daily Thermal Predictions of the AGR-2 Experiment in the Advanced Test Reactor
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Topics: Finite element analysis, Fluence (Radiation measurement), Fuels, Graphite, Heat, Neutrons, Particulate matter, Stainless steel, Temperature, Thermal conductivity
Proceedings Papers

Zirconium Dioxide as a Protective Layer of Zirconium Fuel Cladding

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Barbora Benešová, Radek Škoda
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A018, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30848
https://doi.org/10.1115/ICONE22-30848
View Paper titled, Zirconium Dioxide as a Protective Layer of Zirconium Fuel Cladding
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Topics: Cladding systems (Building), Fuels, Zirconium, Oxidation, Stress, Temperature, Accidents, Ceramics, Cooling, Corrosion
Proceedings Papers

Neutron Exposure and Electrical Analysis of P-Type Boron-Doped Silicon Resistors and Transistors

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Hector E. Medina, Brian Hinderliter
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A055, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30845
https://doi.org/10.1115/ICONE22-30845
View Paper titled, Neutron Exposure and Electrical Analysis of P-Type Boron-Doped Silicon Resistors and Transistors
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Topics: Boron, Neutrons, Resistors, Silicon, Transistors, Gates (Closures), Helium, Sensors, Design, Electrical conductance
Proceedings Papers

Role of Irradiation Embrittlement in RPV Lifetime Assessment

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Milan Brumovský, Miloš Kytka
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A013, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15420
https://doi.org/10.1115/ICONE21-15420
View Paper titled, Role of Irradiation Embrittlement in RPV Lifetime Assessment
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Topics: Embrittlement, Irradiation (Radiation exposure), Design, Radiation damage, Engineering standards, Failure, Fluence (Radiation measurement), Fracture mechanics, Hardening, Neutron flux
Proceedings Papers

3D Calculations of PWR Vessels Neutron Fluence With EFLUVE 3D Code

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Cécile-Aline Gosmain, Sylvain Rollet, Damien Schmitt
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A035, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16316
https://doi.org/10.1115/ICONE21-16316
View Paper titled, 3D Calculations of PWR Vessels Neutron Fluence With EFLUVE 3D Code
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Topics: Fluence (Radiation measurement), Neutrons, Pressurized water reactors, Vessels, Neutron sources, Surveillance, Chemical kinetics, Pressure vessels, Dosimeters, Dosimetry
Proceedings Papers

EFLUVE3D Code: A 3D Tool for the Neutron Fluence Calculations on Pressurized Water Reactor Vessels

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Cécile-Aline Gosmain, Sylvain Rollet, Damien Schmitt
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 481-489, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54965
https://doi.org/10.1115/ICONE20-POWER2012-54965
View Paper titled, EFLUVE3D Code: A 3D Tool for the Neutron Fluence Calculations on Pressurized Water Reactor Vessels
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Topics: Fluence (Radiation measurement), Neutrons, Pressurized water reactors, Vessels, Neutron sources, Surveillance, Dosimeters, Pressure vessels, Chemical kinetics, Dosimetry
Proceedings Papers

Investigation on Integrity of JMTR Reactor Pressure Vessel

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Hiroshi Ide, Akihiro Kimura, Hiroshi Miura, Yoshiharu Nagao, Naohiko Hori, Masanori Kaminaga
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 325-334, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30238
https://doi.org/10.1115/ICONE18-30238
View Paper titled, Investigation on Integrity of JMTR Reactor Pressure Vessel
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Topics: Reactor vessels, Adhesion, Fatigue, Fluence (Radiation measurement), Iron, Materials testing, Neutrons, Nozzles, Screws, Stress corrosion cracking
Proceedings Papers

Life Extension of the Fast Breeder Test Reactor

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B. Anandapadmanaban, A. Babu, B. Babu, K. Dinesh, V. Ramanathan, G. Srinivasan
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 97-102, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29277
https://doi.org/10.1115/ICONE18-29277
View Paper titled, Life Extension of the Fast Breeder Test Reactor
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Topics: Life extension, Fuels, Heat, Creep, Cycles, Design, Equipment qualification, Maintenance, Pumps, Safety
Proceedings Papers

Simulation of CCD Degradation Induced by Protons Irradiation

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Zujun Wang, Shaoyan Huang, Minbo Liu, Benqi Tang, Zhigang Xiao, Yong Zhang
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 105-109, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29302
https://doi.org/10.1115/ICONE18-29302
View Paper titled, Simulation of CCD Degradation Induced by Protons Irradiation
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Topics: Irradiation (Radiation exposure), Protons, Simulation, Signals, Damage, Displacement, Ionization, Charge transfer, Fluence (Radiation measurement), Simulation models
Proceedings Papers

The Design of a Neutron Dosimeter

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Wenming Xia, Mingchun Jia, Zhirong Guo
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 7-15, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29047
https://doi.org/10.1115/ICONE18-29047
View Paper titled, The Design of a Neutron Dosimeter
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Topics: Design, Dosimeters, Neutrons, Radiation (Physics), Sensors, Electronic systems, Fluence (Radiation measurement), Matlab
Proceedings Papers

Prediction of Irradiation Embrittlement for Chinese Domestic A508-3 Steel

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Feng Lu, Rongshan Wang, Ping Huang, Haiyang Qian
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 487-491, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29389
https://doi.org/10.1115/ICONE18-29389
View Paper titled, Prediction of Irradiation Embrittlement for Chinese Domestic A508-3 Steel
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Topics: Embrittlement, Irradiation (Radiation exposure), Steel, Nuclear power stations, Safety, Fluence (Radiation measurement), Fracture toughness, Neutrons, Reactor vessels, Regulations