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Proceedings Papers

Westinghouse eVinci™ Heat Pipe Micro Reactor Technology Development

Matt M. Swartz, William A. Byers, John Lojek, Rory Blunt
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, V001T04A018, August 4–6, 2021
Paper No: ICONE28-67519
DOI: https://doi.org/10.1115/ICONE28-67519
View Paper titled, Westinghouse eVinci™ Heat Pipe Micro Reactor Technology Development
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Topics: Heat pipes, Technology development
Proceedings Papers

Heat Transfer and Fluid Flow Characteristic of One Side Heated Vertical Rectangular Channel That Inserted Thin Metallic Wire

Gota Suga, Tetsuaki Takeda
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A040, August 4–5, 2020
Paper No: ICONE2020-16705
DOI: https://doi.org/10.1115/ICONE2020-16705
View Paper titled, Heat Transfer and Fluid Flow Characteristic of One Side Heated Vertical Rectangular Channel That Inserted Thin Metallic Wire
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Topics: Fluid dynamics, Heat transfer, Wire, Very high temperature reactors, Flow (Dynamics), Natural convection, Cooling, Cooling systems, Copper, Gas turbines
Proceedings Papers

Heat Transfer and Fluid Flow Characteristics of One Side Heated Vertical Rectangular Channel Applied As Vessel Cooling System of VHTR

Kenta Fujikami, Tetsuaki Takeda, Shumpei Funatani
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A046, July 22–26, 2018
Paper No: ICONE26-81700
DOI: https://doi.org/10.1115/ICONE26-81700
View Paper titled, Heat Transfer and Fluid Flow Characteristics of One Side Heated Vertical Rectangular Channel Applied As Vessel Cooling System of VHTR
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Topics: Cooling systems, Fluid dynamics, Heat transfer, Very high temperature reactors, Vessels, Flow (Dynamics), Natural convection, Porosity, Porous materials, Cooling
Proceedings Papers

The Application of Heat Pipe Discharge Containment Heat Experimental Study: New Type of Passive Containment Heat Removal System Concept Design

Haiqi Qin, Daogang Lu, Shengfei Wang
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A082, July 2–6, 2017
Paper No: ICONE25-67134
DOI: https://doi.org/10.1115/ICONE25-67134
View Paper titled, The Application of Heat Pipe Discharge Containment Heat Experimental Study: New Type of Passive Containment Heat Removal System Concept Design
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Topics: Containment, Design, Heat, Heat pipes, Accidents, Conceptual design, Nuclear power, Cooling, Experimental design, Heat transfer
Proceedings Papers

Technology Development on Reactor Dismantling and Investigation of Contamination in FUGEN

Goro Soejima, Hiroki Iwai, Yasuyuki Nakamura, Hirokazu Hayashi, Haruhiko Kadowaki, Hiroyuki Mizui, Kazuya Sano
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A019, July 2–6, 2017
Paper No: ICONE25-66950
DOI: https://doi.org/10.1115/ICONE25-66950
View Paper titled, Technology Development on Reactor Dismantling and Investigation of Contamination in FUGEN
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Topics: Contamination, Technology development, Laser cutting, Cutting, Nuclear decommissioning, Water, Pipes, Zirconium alloys, Aluminum, Boiling
Proceedings Papers

The Research of Integration of Design and Analysis Based on 3D Design Platform of NPP

Xiao Yu
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A089, July 2–6, 2017
Paper No: ICONE25-67247
DOI: https://doi.org/10.1115/ICONE25-67247
View Paper titled, The Research of Integration of Design and Analysis Based on 3D Design Platform of NPP
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Topics: Design, Nuclear power stations, Engineering disciplines, Modeling, Nuclear power, Product design, Technology development
Proceedings Papers

Application Differences of In-Service Inspection Regulations Between RSE-M2010 and ASME Section XI in China PWRs

Yang Cheng, Zhang Xueliang, Xia Peng, Zeng Qingyue, Li Tian
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T07A001, July 2–6, 2017
Paper No: ICONE25-66028
DOI: https://doi.org/10.1115/ICONE25-66028
View Paper titled, Application Differences of In-Service Inspection Regulations Between RSE-M2010 and ASME Section XI in China PWRs
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Topics: China, In-service inspection, Pressurized water reactors, Regulations, Nuclear power, Innovation, Inspection, Licensing, Nondestructive evaluation, Nuclear industry
Proceedings Papers

Activities of the Safety and Operation Project for the International Research and Development of the Sodium-Cooled Fast Reactor in the Generation IV International Forum

Takaaki Sakai, Lixia Ren, Haileyesus Tsige-Tamirat, Alfredo Vasile, Seok-Hun Kang, Yury Ashurko, Thomas Fanning
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, V002T06A021, June 26–30, 2016
Paper No: ICONE24-60502
DOI: https://doi.org/10.1115/ICONE24-60502
View Paper titled, Activities of the Safety and Operation Project for the International Research and Development of the Sodium-Cooled Fast Reactor in the Generation IV International Forum
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Topics: Industrial research, Safety, Sodium fast reactors, Testing, Design, Generation IV reactors, Licensing, Maintenance, Model validation, Nuclear power
Proceedings Papers

Post-Fukushima Research and Development Strategies and Priorities for Water Cooled Reactor Technology Development

Katsumi Yamada, Abdallah Amri, Lyndon Bevington, Pal Vincze
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T13A019, June 26–30, 2016
Paper No: ICONE24-60877
DOI: https://doi.org/10.1115/ICONE24-60877
View Paper titled, Post-Fukushima Research and Development Strategies and Priorities for Water Cooled Reactor Technology Development
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Topics: Fukushima nuclear disaster, Japan, 2011, Industrial research, Technology development, Water, Accidents, Nuclear power stations, Collaboration, Earthquakes, Safety, Shorelines
Proceedings Papers

Experimental Activity for the Investigation of Mixing and Thermal Stratification Phenomena in the CIRCE Pool Facility

D. Martelli, M. Tarantino, I. Di Piazza
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A027, June 26–30, 2016
Paper No: ICONE24-60920
DOI: https://doi.org/10.1115/ICONE24-60920
View Paper titled, Experimental Activity for the Investigation of Mixing and Thermal Stratification Phenomena in the CIRCE Pool Facility
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Topics: Thermal stratification, Fuels, Fast neutron reactors, Safety, Design, Flow (Dynamics), Heat, Heat sinks, Heat transfer, Liquid metals
Proceedings Papers

Design Improvement Studies for Future SFR

Rajan Babu V., V. Balasubramaniyan, Raghupathy Sundararajan, P. Puthiyavinayagam, Chellapandi Perumal
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A021, July 7–11, 2014
Paper No: ICONE22-30742
DOI: https://doi.org/10.1115/ICONE22-30742
View Paper titled, Design Improvement Studies for Future SFR
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Topics: Design, Sodium fast reactors, Manufacturing, Sodium, Construction, Heat, Vessels, Breeder reactors, Circuits, Dimensions
Proceedings Papers

HELENA: A Heavy Liquid Metal Multi-Purpose Loop for Thermal-Hydraulics, Corrosion and Component Test

I. Di Piazza, M. Tarantino, P. Agostini, P. Gaggini
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A022, July 7–11, 2014
Paper No: ICONE22-30784
DOI: https://doi.org/10.1115/ICONE22-30784
View Paper titled, HELENA: A Heavy Liquid Metal Multi-Purpose Loop for Thermal-Hydraulics, Corrosion and Component Test
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Topics: Corrosion, Liquid metals, Thermal hydraulics, Pumps, Flow (Dynamics), High temperature, Oxygen, Pressure, Shells, Water
Proceedings Papers

HLM Fuel Pin Bundle Characterization in CIRCE Pool Facility

M. Tarantino, D. Martelli, I. Di Piazza, N. Forgione, P. Agostini, G. Coccoluto
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A022, July 7–11, 2014
Paper No: ICONE22-30774
DOI: https://doi.org/10.1115/ICONE22-30774
View Paper titled, HLM Fuel Pin Bundle Characterization in CIRCE Pool Facility
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Topics: Fuels, Coolants, Pins (Engineering), Cladding systems (Building), Competencies, Computational fluid dynamics, Corrosion, Fast neutron reactors, Heat transfer, Heat transfer coefficients
Proceedings Papers

Development of Glass Melter Technology for HLLW Vitrification in Japan

Akira Sakai, Hajime Koikegami, Nobuyuki Miura, Eiji Ochi
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, V004T08A011, July 7–11, 2014
Paper No: ICONE22-30693
DOI: https://doi.org/10.1115/ICONE22-30693
View Paper titled, Development of Glass Melter Technology for HLLW Vitrification in Japan
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Topics: Glass, Vitrification, Metals, Design, Testing, Ceramics, Glassmaking, Joules, Precipitation, Process design
Proceedings Papers

The Principle and Preliminary Validation of a New Subchannel Code

Ning Bai, Yuanbing Zhu, Zhihao Ren, Haibo He, Haoliang Lu, Jun Chen, Wenhuai Li, Jinggang Li
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A038, July 29–August 2, 2013
Paper No: ICONE21-15464
DOI: https://doi.org/10.1115/ICONE21-15464
View Paper titled, The Principle and Preliminary Validation of a New Subchannel Code
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Topics: Algorithms, China, Constitutive equations, Design, Fuel rods, Heat transfer, Nuclear design, Nuclear power, Nuclear power stations, Numerical analysis
Proceedings Papers

The Screening Methodologies and/or Achievement Evaluation in Japanese FR Cycle Development Program With the Changing Needs for Evaluation

Hiroki Shiotani, Nariaki Uto, Koichi Kawaguchi, Yoshihiko Shinoda, Kiyoshi Ono, Takashi Namba
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 693-702, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54933
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54933
View Paper titled, The Screening Methodologies and/or Achievement Evaluation in Japanese FR Cycle Development Program With the Changing Needs for Evaluation
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Topics: Cycles, Design, Fast neutron reactors, Nuclear fuel cycle, Conceptual design, Fuels, Governments, Manufacturing, Pelletizing, Performance evaluation
Proceedings Papers

Steam Generator Asset Management Program

Padmanabha J. Prabhu, Damian A. Testa
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 171-176, May 17–21, 2010
Paper No: ICONE18-29471
DOI: https://doi.org/10.1115/ICONE18-29471
View Paper titled, Steam Generator Asset Management Program
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Topics: Boilers, Maintenance, Strategic planning, Inspection, Pressurized water reactors, Chemistry, Condition monitoring, Cost benefit analysis, Decision making, Life extension
Proceedings Papers

Development of Advanced Loop-Type Fast Reactor in Japan: Progress of Design Study Based on Preliminary Assessment Results

Yoshihiko Sakamoto, Shoji Kotake, Kazumi Aoto, Mikio Toda
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 355-363, May 17–21, 2010
Paper No: ICONE18-30322
DOI: https://doi.org/10.1115/ICONE18-30322
View Paper titled, Development of Advanced Loop-Type Fast Reactor in Japan: Progress of Design Study Based on Preliminary Assessment Results
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Topics: Design, Fast neutron reactors, Nuclear reactors, Reactor vessels, Circuits, Cooling, Cycles, Damage, Optimization, Piping design
Proceedings Papers

Status of Future Reactor Technology Development in Korea

Dohee Hahn, Yeong-Il Kim, Yong Wan Kim
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 259-267, May 17–21, 2010
Paper No: ICONE18-29986
DOI: https://doi.org/10.1115/ICONE18-29986
View Paper titled, Status of Future Reactor Technology Development in Korea
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Topics: Technology development, Sodium fast reactors, Very high temperature reactors, Design, Hydrogen, Construction, Hydrogen production, Nuclear power, Nuclear reactors
Proceedings Papers

Current Status of Conceptual Design Study Toward the Demonstration Reactor of JSFR

Takaaki Sakai, Shoji Kotake, Kazumi Aoto, Takaya Ito, Yoshio Kamishima, Jun Ohshima
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 333-340, May 17–21, 2010
Paper No: ICONE18-30172
DOI: https://doi.org/10.1115/ICONE18-30172
View Paper titled, Current Status of Conceptual Design Study Toward the Demonstration Reactor of JSFR
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Topics: Conceptual design, Construction, Cycles, Design, Fast neutron reactors, Licensing, Plant design, Sodium fast reactors, Technology development