1-20 of 312
Light water reactors
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Molten Salt Reactor Simulation by a MOOSE-Based Application Suanni

Ao Zhang, Ming Dai, Shaopeng Xia, Jingen Chen, Xiangzhou Cai
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
https://doi.org/10.1115/ICONE31-136944
View Paper titled, Molten Salt Reactor Simulation by a MOOSE-Based Application Suanni
Open the PDF for Molten Salt Reactor Simulation by a MOOSE-Based Application Suanni in another window
Topics: Cross section (Physics), Molten salt reactors, Simulation, Errors, Diffusion (Physics), Finite element methods, Fuels, Light water reactors, Thermal reactors
Proceedings Papers

Design and Analysis of a Nuclear Hydrogen Production System by Methanol Reforming Using Light Water Reactor (LWR)

Ruiyang Liu, Zhiyi Peng, Huaqiang Yin, Huang Zhang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A001, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-123745
https://doi.org/10.1115/ICONE31-123745
View Paper titled, Design and Analysis of a Nuclear Hydrogen Production System by Methanol Reforming Using Light Water Reactor (LWR)
Open the PDF for Design and Analysis of a Nuclear Hydrogen Production System by Methanol Reforming Using Light Water Reactor (LWR) in another window
Topics: Design, Hydrogen production, Light water reactors, Methanol, Nuclear reactors, Steam reforming, Water
Proceedings Papers

Criteria for Selecting Nuclear Reactors for Merchant Shipping

Jan Emblemsvåg, César Hueso Ordóñez, Cristian Garrido Tamm, Terje Strand, Helge Thoresen, Javier Santos Ortigosa, Alejandría Pérez, Yolanda Mugica Colilles, Alba Esteban Izquierdo
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A043, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135177
https://doi.org/10.1115/ICONE31-135177
View Paper titled, Criteria for Selecting Nuclear Reactors for Merchant Shipping
Open the PDF for Criteria for Selecting Nuclear Reactors for Merchant Shipping in another window
Topics: Nuclear reactors, Ships, Small modular reactors, Emissions, Fuel oils, Fuels, Greenhouse gases, Life cycle costing, Light water reactors, Molten salt reactors
Proceedings Papers

Status of the Light-Water, Small, Modular Reactors Research at Oregon State University

Izabela Gutowska, Trevor Kent Howard, Qiao Wu, Brian G. Woods
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A061, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135989
https://doi.org/10.1115/ICONE31-135989
View Paper titled, Status of the Light-Water, Small, Modular Reactors Research at Oregon State University
Open the PDF for Status of the Light-Water, Small, Modular Reactors Research at Oregon State University in another window
Topics: Control rooms, Small modular reactors, Water, Test facilities, Dynamic systems, Licensing, Light water reactors, Performance, Pressure, Temperature
Proceedings Papers

Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor

Takeshi Koike, Koji Asano, Mizuki Yamada, Satoru Kamohara, Tadakatsu Yodo, Nozomu Murakami
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A037, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135017
https://doi.org/10.1115/ICONE31-135017
View Paper titled, Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor
Open the PDF for Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor in another window
Topics: Design, Heat transfer, Neutrons, Safety, Reliability, Carbon, Fuels, Graphite, Heat, Light water reactors
Proceedings Papers

Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation

Shuowang Fan, Yutong Chen, Dalin Zhang, Xiaoli Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134796
https://doi.org/10.1115/ICONE31-134796
View Paper titled, Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation
Open the PDF for Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation in another window
Topics: Fast neutron reactors, Stainless steel, Coolants, Temperature, Accidents, Pressure, Safety, Sodium, Temperature distribution, Vessels
Proceedings Papers

Development of a New Crust Model for Analyzing VULCANO VBS-U3 MCCI Experiment With MPS Method

Takeshi Yamada, Xin Li, Takuya Yamashita, Akifumi Yamaji
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134499
https://doi.org/10.1115/ICONE31-134499
View Paper titled, Development of a New Crust Model for Analyzing VULCANO VBS-U3 MCCI Experiment With MPS Method
Open the PDF for Development of a New Crust Model for Analyzing VULCANO VBS-U3 MCCI Experiment With MPS Method in another window
Topics: Ablation (Vaporization technology), Accidents, Chaos, Computation, Computational fluid dynamics, Computer simulation, Concrete walls, Concretes, Containment, Displacement
Proceedings Papers

Total Monte Carlo Uncertainty Analysis of VVER-440 Spent Nuclear Fuel in LWR and HWR Reactor Environment

Martin Lovecký, Jiří Závorka, Tomáš Kořínek, Radek Škoda
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A050, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136014
https://doi.org/10.1115/ICONE31-136014
View Paper titled, Total Monte Carlo Uncertainty Analysis of VVER-440 Spent Nuclear Fuel in LWR and HWR Reactor Environment
Open the PDF for Total Monte Carlo Uncertainty Analysis of VVER-440 Spent Nuclear Fuel in LWR and HWR Reactor Environment in another window
Topics: Heat, Heavy water reactors, Light water reactors, Spent nuclear fuels, Uncertainty analysis
Proceedings Papers

Multiphysics Analysis of UN Fuel Performance With a Two-Layered SiC Cladding Under Multiple Operating Conditions in a Light Water Reactor

Rong Liu, Huiyun Han, Shengyu Liu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A068, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91980
https://doi.org/10.1115/ICONE29-91980
View Paper titled, Multiphysics Analysis of UN Fuel Performance With a Two-Layered SiC Cladding Under Multiple Operating Conditions in a Light Water Reactor
Open the PDF for Multiphysics Analysis of UN Fuel Performance With a Two-Layered SiC Cladding Under Multiple Operating Conditions in a Light Water Reactor in another window
Topics: Accidents, Cladding systems (Building), Fuels, Light water reactors
Proceedings Papers

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Jie Wang, Yang Wang, Jun Wei, Yongjun Deng
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90521
https://doi.org/10.1115/ICONE29-90521
View Paper titled, Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition
Open the PDF for Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition in another window
Topics: Cladding systems (Building), Ductility, Equipment performance, Hydrogen, Zirconium alloys, Zirconium, Accidents, Failure, Fracture (Process), Light water reactors
Proceedings Papers

Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6

Chang Zhang, Ruixiang Wang, Hui Guo, Hanyang Gu, Yao Xiao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A101, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92642
https://doi.org/10.1115/ICONE29-92642
View Paper titled, Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6
Open the PDF for Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6 in another window
Topics: Physics, Thermal hydraulics, Fuels, Temperature, Coolants, Light water reactors, Manufacturing, Simulation, Eigenvalues, Fuel rods
Proceedings Papers

Development of a Numerical Simulation Method for Air Cooling of Fuel Debris by JUPITER

Susumu Yamashita, Shinichiro Uesawa, Hiroyuki Yoshida
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89345
https://doi.org/10.1115/ICONE29-89345
View Paper titled, Development of a Numerical Simulation Method for Air Cooling of Fuel Debris by JUPITER
Open the PDF for Development of a Numerical Simulation Method for Air Cooling of Fuel Debris by JUPITER in another window
Topics: Computer simulation, Cooling, Fuels, Natural convection, Porous materials, Temperature, Accidents, Boiling water reactors, Computational fluid dynamics, Containment vessels
Proceedings Papers

Study on Methodology for Quantification of Radioactive Discharges and Limits for Pressurized Water Reactor HPR1000 Based on Operating Experience

Yujia Chen, Weifeng Lv, Zhenyu Jiang, Yonghai Zhou
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A024, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92385
https://doi.org/10.1115/ICONE29-92385
View Paper titled, Study on Methodology for Quantification of Radioactive Discharges and Limits for Pressurized Water Reactor HPR1000 Based on Operating Experience
Open the PDF for Study on Methodology for Quantification of Radioactive Discharges and Limits for Pressurized Water Reactor HPR1000 Based on Operating Experience in another window
Topics: Pressurized water reactors, Design, Nuclear power stations, Fluctuations (Physics), Light water reactors, Modeling, Radiation (Physics)
Proceedings Papers

Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers: Unit Cell Model

Xicheng Wang, Dmitry Grishchenko, Pavel Kudinov
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A084, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65751
https://doi.org/10.1115/ICONE28-65751
View Paper titled, Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers: Unit Cell Model
Open the PDF for Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers: Unit Cell Model in another window
Topics: Condensation, Environmental health and safety, Momentum, Steam, Thermal stratification, Turbulence, Heat, Boundary-value problems, Containment, Modeling
Proceedings Papers

Study on Collapsed Cross Section for Radial Reflector in LWR

Ryosuke 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
https://doi.org/10.1115/ICONE28-65686
View Paper titled, Study on Collapsed Cross Section for Radial Reflector in LWR
Open the PDF for Study on Collapsed Cross Section for Radial Reflector in LWR in another window
Topics: Cross section (Physics), Light water reactors
Proceedings Papers

Improvement of Conversion Ratio of Thorium Fuel in LWR by Adding Neutron Absorber

Taichi Takeishi, Satoshi Takeda, Takanori Kitada
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A078, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65683
https://doi.org/10.1115/ICONE28-65683
View Paper titled, Improvement of Conversion Ratio of Thorium Fuel in LWR by Adding Neutron Absorber
Open the PDF for Improvement of Conversion Ratio of Thorium Fuel in LWR by Adding Neutron Absorber in another window
Topics: Fuels, Light water reactors, Neutrons
Proceedings Papers

Evaluation of the Applicability of Plutonium Transmuted From Minor Actinides by Fusion Reactor as Fertile Fuel in Boiling Water Reactor

Masaki Shimizu, Hiroki Shishido, Hidetoshi Hashizume
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A014, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65139
https://doi.org/10.1115/ICONE28-65139
View Paper titled, Evaluation of the Applicability of Plutonium Transmuted From Minor Actinides by Fusion Reactor as Fertile Fuel in Boiling Water Reactor
Open the PDF for Evaluation of the Applicability of Plutonium Transmuted From Minor Actinides by Fusion Reactor as Fertile Fuel in Boiling Water Reactor in another window
Topics: Boiling water reactors, Fuels, Fusion reactors, Light water reactors
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
Open the PDF for ARKADIA – for the Innovation of Advanced Nuclear Reactor Design in another window
Topics: Artificial intelligence, Computer simulation, Innovation, Nuclear design, Nuclear reactors, Optimization, Design, Safety, Carbon, Coolants
Proceedings Papers

A Finnish District Heating Reactor: Background and General Overview

Jaakko Leppänen, Seppo Hillberg, Ville Hovi, Rebekka Komu, Joona Kurki, Unna Lauranto, Ahti Oinonen, Jussi Peltonen, Antti Rintala, Ville Tulkki, Riku Tuominen, Ville Valtavirta
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, V001T04A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64346
https://doi.org/10.1115/ICONE28-64346
View Paper titled, A Finnish District Heating Reactor: Background and General Overview
Open the PDF for A Finnish District Heating Reactor: Background and General Overview in another window
Topics: Central heating, Design, Coal, Governments, Heat, Boilers, Carbon, Climate, Containment, Energy generation
Proceedings Papers

Recent Activities and New Challenges for the EUR Organization

Vincent Sorel
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, V001T02A026, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64617
https://doi.org/10.1115/ICONE28-64617
View Paper titled, Recent Activities and New Challenges for the EUR Organization
Open the PDF for Recent Activities and New Challenges for the EUR Organization in another window
Topics: Accidents, Design, Engineering standards, Fukushima nuclear disaster, Japan, 2011, Light water reactors, Nuclear power stations, Safety, Small modular reactors