1-20 of 68
Isotopes
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

Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement

Kai Tan, Ruihan Li, Jian Li, Jingang Liang, Ding She
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A053, August 8–12, 2022
Paper No: ICONE29-91659
DOI: https://doi.org/10.1115/ICONE29-91659
View Paper titled, Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement
Open the PDF for Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement in another window
Topics: Nuclides, Pressurized water reactors, Spent nuclear fuels, Density, Errors, Accuracy and precision, Fuels, Heat, Isotopes, Nuclear fission
Proceedings Papers

Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium

Ziling Zhou, Yu Wang, Jingni Guo, Feng Xie, Wenqian Li, Yanwei Wen, Bin Shan
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A039, August 8–12, 2022
Paper No: ICONE29-91275
DOI: https://doi.org/10.1115/ICONE29-91275
View Paper titled, Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium
Open the PDF for Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium in another window
Topics: Hydraulic conductivity, Very high temperature reactors, Fusion reactors, Hydrogen, Isotopes, Nuclear reactors, Coolants, Design, Diffusion (Physics), Engineering systems and industry applications
Proceedings Papers

Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis

Zihao Guo, Guang Wang, Genghua Su, Xiuan Shi
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A036, August 8–12, 2022
Paper No: ICONE29-93256
DOI: https://doi.org/10.1115/ICONE29-93256
View Paper titled, Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis
Open the PDF for Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis in another window
Topics: Design, Irradiation (Radiation exposure), Neutron flux, Physics, Water, Biomedicine, Isotopes, Cycles, Decontamination, Fuels
Proceedings Papers

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

Jian Li, Ruihan Li, Ding She, Jin'gang Liang, Lei Shi
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 8–12, 2022
Paper No: ICONE29-89241
DOI: https://doi.org/10.1115/ICONE29-89241
View Paper titled, Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies
Open the PDF for Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies in another window
Topics: Heat, Pressurized water reactors, Spent nuclear fuels, Fuels, Neutrons, Boiling water reactors, Collapse, Cooling, Cross section (Physics), Density
Proceedings Papers

Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor

Songyang Liu, Xiang Wang
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, V001T04A014, August 4–6, 2021
Paper No: ICONE28-65689
DOI: https://doi.org/10.1115/ICONE28-65689
View Paper titled, Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor
Open the PDF for Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor in another window
Topics: Isotopes, Neutrons, Optimization, Physics, Small modular reactors, Temperature, Cycles, Design, Fuels, China
Proceedings Papers

Research on Tritium Behavior Issues in High-Temperature Gas-Cooled Reactors

Ziling Zhou, Chuan Li, Nan Gui, Feng Xie, Yanwei Wen, Bin Shan, Jia Fu, Qunchao Fan
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A016, August 4–6, 2021
Paper No: ICONE28-63539
DOI: https://doi.org/10.1115/ICONE28-63539
View Paper titled, Research on Tritium Behavior Issues in High-Temperature Gas-Cooled Reactors
Open the PDF for Research on Tritium Behavior Issues in High-Temperature Gas-Cooled Reactors in another window
Topics: Diffusion (Physics), Isotopes, Very high temperature reactors, Coolants, Graphite, Absorption, Desorption, Safety, Engineering prototypes, Fuels
Proceedings Papers

Evaluation of Decay Dose Rates for European DEMO Vacuum Vessel Structure

Simona Breidokaitė, Andrius Tidikas, Gediminas Stankūnas
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A031, August 4–5, 2020
Paper No: ICONE2020-16465
DOI: https://doi.org/10.1115/ICONE2020-16465
View Paper titled, Evaluation of Decay Dose Rates for European DEMO Vacuum Vessel Structure
Open the PDF for Evaluation of Decay Dose Rates for European DEMO Vacuum Vessel Structure in another window
Topics: Vacuum, Vessels, Cooling, Shells, Water, Isotopes, Neutrons, Radioisotopes, Stainless steel, Design
Proceedings Papers

Influence of Xe-135 Dynamic Behavior on Core Operation Safety for a Molten Salt Reactor

Wu Jian-hui, Li Xiao-xiao, Hu Ji-feng, Chen Jin-gen, Yu Cheng-gang, Zou Chun-yan, Cai Xiang-zhou
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A050, July 22–26, 2018
Paper No: ICONE26-82352
DOI: https://doi.org/10.1115/ICONE26-82352
View Paper titled, Influence of Xe-135 Dynamic Behavior on Core Operation Safety for a Molten Salt Reactor
Open the PDF for Influence of Xe-135 Dynamic Behavior on Core Operation Safety for a Molten Salt Reactor in another window
Topics: Molten salt reactors, Safety, Neutrons, Fuels, Helium, Nuclear reactors, Absorption, Chain, Computational methods, Density
Proceedings Papers

Analysis of Major Group Structures Used for Nuclear Reactor Simulations

Marco Di Filippo, Jiri Krepel, Konstantin Mikityuk, Horst-Michael Prasser
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A029, July 22–26, 2018
Paper No: ICONE26-81445
DOI: https://doi.org/10.1115/ICONE26-81445
View Paper titled, Analysis of Major Group Structures Used for Nuclear Reactor Simulations
Open the PDF for Analysis of Major Group Structures Used for Nuclear Reactor Simulations in another window
Topics: Nuclear reactors, Simulation, Cross section (Physics), Resolution (Optics), Fast neutron reactors, Isotopes
Proceedings Papers

Proven Technologies for the Solidification of Complex Liquid Radioactive Waste (LRW): Global Case Studies of Applications and Disposal Options

Dennis Kelley
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A002, July 2–6, 2017
Paper No: ICONE25-66081
DOI: https://doi.org/10.1115/ICONE25-66081
View Paper titled, Proven Technologies for the Solidification of Complex Liquid Radioactive Waste (LRW): Global Case Studies of Applications and Disposal Options
Open the PDF for Proven Technologies for the Solidification of Complex Liquid Radioactive Waste (LRW): Global Case Studies of Applications and Disposal Options in another window
Topics: Radioactive wastes, Solidification, Nuclear power stations, Hazards, Isotopes, Nuclear decommissioning, Polymers, Storage, Warfare
Proceedings Papers

Analysis on Radioactive Gas Movement and Delay Status Before Release

Bo Nan Zhu
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A017, July 2–6, 2017
Paper No: ICONE25-66713
DOI: https://doi.org/10.1115/ICONE25-66713
View Paper titled, Analysis on Radioactive Gas Movement and Delay Status Before Release
Open the PDF for Analysis on Radioactive Gas Movement and Delay Status Before Release in another window
Topics: Delays, Activated carbon, Design, Dimensions, Flow (Dynamics), Computational methods, Design methodology, Isotopes, Nuclear fission, Nuclear power stations
Proceedings Papers

Qualification Requirements Design for Neutron Absorber Plate for Spent Fuel Racks in Domestic Nuclear Power Plants

You Shi, Dong Ning, Yi-zhong Yang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A026, July 2–6, 2017
Paper No: ICONE25-66256
DOI: https://doi.org/10.1115/ICONE25-66256
View Paper titled, Qualification Requirements Design for Neutron Absorber Plate for Spent Fuel Racks in Domestic Nuclear Power Plants
Open the PDF for Qualification Requirements Design for Neutron Absorber Plate for Spent Fuel Racks in Domestic Nuclear Power Plants in another window
Topics: Design, Neutrons, Nuclear power stations, Spent nuclear fuels, China, Density, Manufacturing, Spent fuel storage, Testing, Aluminum
Proceedings Papers

Effect of Spray System on in Containment Fission Product Washout During In-Vessel Release Phase

Khurram Mehboob, Mohammad. S. Aljohani
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A005, July 2–6, 2017
Paper No: ICONE25-66056
DOI: https://doi.org/10.1115/ICONE25-66056
View Paper titled, Effect of Spray System on in Containment Fission Product Washout During In-Vessel Release Phase
Open the PDF for Effect of Spray System on in Containment Fission Product Washout During In-Vessel Release Phase in another window
Topics: Containment, Nuclear fission, Sprays, Vessels, Drops, Absorption, Radioisotopes, Sensitivity analysis, Accidents, Computer simulation
Proceedings Papers

Research on Nickel-Plated Hydrogen-Absorption Device in Fuel Rod and Performance Testing

Zhou Qin, Li Jiwei, Dang Yu, Ding Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A041, July 2–6, 2017
Paper No: ICONE25-67112
DOI: https://doi.org/10.1115/ICONE25-67112
View Paper titled, Research on Nickel-Plated Hydrogen-Absorption Device in Fuel Rod and Performance Testing
Open the PDF for Research on Nickel-Plated Hydrogen-Absorption Device in Fuel Rod and Performance Testing in another window
Topics: Absorption, Fuel rods, Hydrogen, Nickel plating, Testing performance, Cladding systems (Building), Design, Pressure, Zirconium, Alloys
Proceedings Papers

Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

Bie Yewang, Li Huwei, Xiong Wenbin, Zhang Donghui, Wu Mingyu, Wang Xinzhe
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A118, July 2–6, 2017
Paper No: ICONE25-67994
DOI: https://doi.org/10.1115/ICONE25-67994
View Paper titled, Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location
Open the PDF for Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location in another window
Topics: China, Fast neutron reactors, Fuels, Manufacturing, Failure, Safety, Cladding systems (Building), Design, Heat transfer, Isotopes
Proceedings Papers

A New Method to Evaluate the Correlation Coefficients Between Nuclides in Uncertainty and Sensitivity Analysis

Xu Jia Yi, Ma Xu Bo, Shen Jing Wen, Liu Jia Yi, Chen Yi Xue
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A028, July 2–6, 2017
Paper No: ICONE25-66777
DOI: https://doi.org/10.1115/ICONE25-66777
View Paper titled, A New Method to Evaluate the Correlation Coefficients Between Nuclides in Uncertainty and Sensitivity Analysis
Open the PDF for A New Method to Evaluate the Correlation Coefficients Between Nuclides in Uncertainty and Sensitivity Analysis in another window
Topics: Nuclides, Sensitivity analysis, Uncertainty, Isotopes, Cross section (Physics), Density, Pressurized water reactors, Cycles, Fast neutron reactors, Nuclear engineering
Proceedings Papers

The Verification of SONG Library

Hua Bei, Jinkun Zhao, Qichang Chen, Shengyi Si
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A036, July 2–6, 2017
Paper No: ICONE25-66946
DOI: https://doi.org/10.1115/ICONE25-66946
View Paper titled, The Verification of SONG Library
Open the PDF for The Verification of SONG Library in another window
Topics: Absorption, Chemical kinetics, Cladding systems (Building), Electromagnetic scattering, Fuels, Isotopes, Molten salt reactors, Nuclear fission, Pressurized water reactors, Radiation scattering
Proceedings Papers

Development and Verification of Multi-Group Cross Section Process Code TXMAT for Fast Reactor RBEC-M Analysis

Ruomeng Qiu, Xubo Ma, Qian Xu, Jiayi Liu, Yixue Chen
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A015, July 2–6, 2017
Paper No: ICONE25-66550
DOI: https://doi.org/10.1115/ICONE25-66550
View Paper titled, Development and Verification of Multi-Group Cross Section Process Code TXMAT for Fast Reactor RBEC-M Analysis
Open the PDF for Development and Verification of Multi-Group Cross Section Process Code TXMAT for Fast Reactor RBEC-M Analysis in another window
Topics: Fast neutron reactors, Cross section (Physics), Absorption, Computer programming, Diffusion (Physics), Errors, Isotopes, Neutrons, Nuclear fission, S-matrix theory
Proceedings Papers

Molecular Dynamics Simulation of the Sputtering of Graphite due to Bombardment With Deuterium and Tritium in Fusion Environment

Qiang Zhao, Yang Li, Zheng Zhang, Xiaoping Ouyang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A064, July 2–6, 2017
Paper No: ICONE25-67781
DOI: https://doi.org/10.1115/ICONE25-67781
View Paper titled, Molecular Dynamics Simulation of the Sputtering of Graphite due to Bombardment With Deuterium and Tritium in Fusion Environment
Open the PDF for Molecular Dynamics Simulation of the Sputtering of Graphite due to Bombardment With Deuterium and Tritium in Fusion Environment in another window
Topics: Graphite, Molecular dynamics simulation, Sputtering (Irradiation), Temperature, Hydrogen, Carbon, Isotopes, Molecular dynamics methods
Proceedings Papers

Detection of Radon-Progeny and Other Alpha-Emitting Radionuclides in Air Using Tensioned Metastable Fluid Detectors

N. Boyle, B. Archambault, A. Hagen, C. Meert, R. P. Taleyarkhan
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A019, July 2–6, 2017
Paper No: ICONE25-66805
DOI: https://doi.org/10.1115/ICONE25-66805
View Paper titled, Detection of Radon-Progeny and Other Alpha-Emitting Radionuclides in Air Using Tensioned Metastable Fluid Detectors
Open the PDF for Detection of Radon-Progeny and Other Alpha-Emitting Radionuclides in Air Using Tensioned Metastable Fluid Detectors in another window
Topics: Fluids, Radioisotopes, Sensors, Temperature, Isotopes, Neutrons, Nuclear fission, Nuclear industry, Temperature effects, Alpha particles