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Proceedings Papers

Code to Code Validation of SAC-3D Based on EBR-II Benchmark Problem

Daogang Lu, Siyu Lyu, Danting Sui
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A006, August 4–5, 2020
Paper No: ICONE2020-16666
DOI: https://doi.org/10.1115/ICONE2020-16666
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Topics: Accidents, Carbon reinforced plastics, China, Electricity (Physics), Fast neutron reactors, Feedback, Flow (Dynamics), Nuclear reactors, Safety, Scram
Proceedings Papers

Development of Single Pebble Benchmark Ex. I-2A for IAEA UAM CRP With MOOSE

Jinlin Niu, Lidong Wang, Jiong Guo, Fu Li
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A033, July 22–26, 2018
Paper No: ICONE26-82155
DOI: https://doi.org/10.1115/ICONE26-82155
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Topics: Carbon reinforced plastics, Temperature, Convection, Coolants, Electrical conductivity, Fuels, Helium, Modeling, Power density, Shells
Proceedings Papers

Thermal-Hydraulic Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment With Modified RELAP5

Tang Simiao, Song Jian, Zhang Dalin, Wang Chenglong, Qiu Suizheng, Su Guanghui, Tian Wenxi
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A023, July 2–6, 2017
Paper No: ICONE25-66766
DOI: https://doi.org/10.1115/ICONE25-66766
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Topics: Flow (Dynamics), Sodium fast reactors, Accidents, Feedback, Coolants, Temperature, Fuels, Pumps, Safety, Sodium
Proceedings Papers

New IAEA Coordinated Research Project on Thermal-Hydraulics of Supercritical Water Cooled Reactors

Katsumi Yamada, Laurence Leung, Walter Ambrosini
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, V002T06A036, June 26–30, 2016
Paper No: ICONE24-60876
DOI: https://doi.org/10.1115/ICONE24-60876
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Topics: Thermal hydraulics, Water, Carbon reinforced plastics, Supercritical water reactors, Collaboration, Performance, Databases
Proceedings Papers

RELAP5-3D Analysis of EBR-II Shutdown Heat Removal Test SHRT-17

Domenico De Luca, Alessandro Petruzzi, Marco Cherubini, Valeria Parrinello
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A046, June 26–30, 2016
Paper No: ICONE24-60629
DOI: https://doi.org/10.1115/ICONE24-60629
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Topics: Heat, Flow (Dynamics), Pumps, Steady state, Transients (Dynamics), Coolants, Metals, Sodium fast reactors, Temperature, Transient analysis
Proceedings Papers

The IAEA Programme in Support of the Development, Design and Safety Analysis of Innovative Fast Neutron Systems

S. Monti, A. Toti
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A026, July 7–11, 2014
Paper No: ICONE22-31051
DOI: https://doi.org/10.1115/ICONE22-31051
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Topics: Design, Neutrons, Safety, Sodium, Sodium fast reactors, Fast neutron reactors, Carbon reinforced plastics, Nuclear power, Chemical properties, Databases
Proceedings Papers

Self-Shielding and Criticality Calculation in Spent Fuel Dissolving Vessel

Qingjie Liu, Hongchun Wu, Liangzhi Cao
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 119-125, May 17–21, 2010
Paper No: ICONE18-29481
DOI: https://doi.org/10.1115/ICONE18-29481
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Topics: Spent nuclear fuels, Vessels, Resonance, Isotopes, Cross section (Physics), Fuels, Pressurized water reactors, Carbon reinforced plastics, Elastic scattering, Fittings
Proceedings Papers

IAEA CRP Benchmark of Kalinin VVER-1000 NPP: An Analysis Using EXCEL-TRIHEX-FA Code System

Suhail Ahmad Khan, V. Jagannathan, R. P. Jain
Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 851-856, May 11–15, 2008
Paper No: ICONE16-48613
DOI: https://doi.org/10.1115/ICONE16-48613
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Topics: Carbon reinforced plastics, Nuclear power stations, Diffusion (Physics), Boron, Construction, Coolants, Density, Feedback, Finite difference methods, Manufacturing