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Proceedings Papers
Molten Salt Reactor Simulation by a MOOSE-Based Application Suanni
Available to Purchase
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A065, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136944
Proceedings Papers
Thermo-Neutronics Coupled Simulation of a Heat Pipe Reactor Based on OpenMC/COMSOL
Available to Purchase
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A047, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135246
Proceedings Papers
Verification of the RMC-SaraGR Nuclear Design Code System Based on the HTTR Benchmark
Available to Purchase
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
Proceedings Papers
Modeling and Analysis of VENUS-2 MOX Core Experiment Based on OpenMC Monte Carlo Code
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Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A001, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130363
Proceedings Papers
Development and Verification of a Few-Group Parameters Calculation Code TMSR-LINK for Molten Salt Reactor
Available to Purchase
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A017, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136987
Proceedings Papers
Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting
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Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A027, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90902
Proceedings Papers
Development and Verification of Multigroup Cross Section Generation Module GroupXS in AXSP
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Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A031, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91399
Proceedings Papers
Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes
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Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92520
Proceedings Papers
Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies
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Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89241
Proceedings Papers
Validation of TULIP via ICSBEP Critical Benchmark
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Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A113, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93353
Proceedings Papers
Evaluation of Serpent Capabilities for Hyperfidelity Depletion of Pebble Bed Cores
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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, V001T04A016, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65810
Proceedings Papers
Study on Collapsed Cross Section for Radial Reflector in LWR
Available to PurchaseRyosuke Shibano, Tatsuya Kawano, Satoshi Takeda, Takanori Kitada, Yoshitada Masaoka, Hiroaki Nagano, Hideaki Hyoudo, Yasuhiro Kodama
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A079, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65686
Proceedings Papers
Mixing Characteristic Measurement of Flow in Reactor Pressure Vessel by Laser Induced Fluorescent Method
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Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A038, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65770
Proceedings Papers
A Neutron Transport Calculation Method for Deep Penetration and its Preliminary Verification
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Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A032, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81709
Proceedings Papers
Analysis and Improvement of Global-Local Self-Shielding Calculation Scheme for AIC Control Rods
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Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A045, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82196
Proceedings Papers
Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC
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Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A005, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81140
Proceedings Papers
Development of Three-Dimensional Neutron Kinetics Code Based on High Order Nodal Expansion Method in Hexagonal-Z Geometry
Available to PurchaseGuo Chao, Liu Yu, He Hangxing, Liu Luguo, Wang Xiaoyu, Xin Sufang, Li Peiyang, Wu Xiaoli, Yuan Hongsheng
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A017, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81356
Proceedings Papers
One Step Method for Multigroup Adjoint Neutron Flux Through Continuous Energy Monte Carlo Calculation
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Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A043, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82185
Proceedings Papers
Towards Development of Uncertainty Library for Nuclear Reactor Core Simulation
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Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A052, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82385
Proceedings Papers
Statistical Burnup Distribution of Moving Pebbles in HTR-PM Reactor
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Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A005, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81082
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