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Proceedings Papers

Isotopic Measurement of HTR-10 Irradiated Fuels Based on Anti-Compton Gamma Spectroscopic Method

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Weijian Zhang, Haiyan Xiao, Jingang Liang, Ruihan Li, Liguo Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A009, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132758
https://doi.org/10.1115/ICONE31-132758
View Paper titled, Isotopic Measurement of HTR-10 Irradiated Fuels Based on Anti-Compton Gamma Spectroscopic Method
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Topics: Fuel management, Fuels, Spent nuclear fuels, Very high temperature reactors, Calibration, China, Isotopes, Measurement uncertainty, Nuclear fission, Optimization
Proceedings Papers

Summary of the History of Improvement and Optimization of Fuel Management Strategies for Two 1000 MWe PWR Units

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Zhou Xiaoling, Xu Zhixian, Zhao Bingquan, Li Wen, Zhong Shengdong, Gao Jinghui
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A070, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92954
https://doi.org/10.1115/ICONE29-92954
View Paper titled, Summary of the History of Improvement and Optimization of Fuel Management Strategies for Two 1000 MWe PWR Units
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Topics: Cycles, Fuel management, Fuels, Leakage, Optimization, Pressurized water reactors
Proceedings Papers

Fuel Management Strategy of LBE-Cooled Fast Reactor BLESS-D

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Zhen Luo, Eing Yee Yeoh, Xiaosong Chen, Linsen Li, Mian Xing
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90443
https://doi.org/10.1115/ICONE29-90443
View Paper titled, Fuel Management Strategy of LBE-Cooled Fast Reactor BLESS-D
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Topics: Cycles, Equilibrium (Physics), Fast neutron reactors, Fuel management
Proceedings Papers

Application of Boron Feedback From BOA CIPS/CILC Analysis on Neutronic Models

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Jesse Fisher, Gary Mangham, Christopher Briggs, Guoqiang Wang, Baocheng Zhang
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A061, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-94476
https://doi.org/10.1115/ICONE29-94476
View Paper titled, Application of Boron Feedback From BOA CIPS/CILC Analysis on Neutronic Models
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Topics: Boron, Feedback, Physics, Fuels, Linkages, Pressurized water reactors, Boiling, Boron compounds, Corrosion, Cycles
Proceedings Papers

Levelized Cost of Electricity Evaluation Methodology Applied to High-Burnup 18 and 24-Month Fuel Cycles

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David L. Stucker, Jeff Norrell, Ho Lam, Fausto Franceschini
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A019, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66589
https://doi.org/10.1115/ICONE28-66589
View Paper titled, Levelized Cost of Electricity Evaluation Methodology Applied to High-Burnup 18 and 24-Month Fuel Cycles
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Topics: Cycles, Fuel management, Fuels, Uranium
Proceedings Papers

Research on Estimating Methods and Application of Fuel Rods Defect

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Huaibin Li, Yaru Fu, Lanfang Mao, Qiliang Mei
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A021, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66622
https://doi.org/10.1115/ICONE25-66622
View Paper titled, Research on Estimating Methods and Application of Fuel Rods Defect
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Topics: Fuel rods, Fuel management, Nuclear fission, Nuclear power stations, Nuclear reactor coolants, Economics , Evaluation methods, Nuclides, Radiation (Physics), Safety
Proceedings Papers

Development and Application of the 3-D Core Fuel Management Transport Program for HFETR

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Lei Zhu, Shouhua Sun, Taozhong Xu
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A017, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60365
https://doi.org/10.1115/ICONE24-60365
View Paper titled, Development and Application of the 3-D Core Fuel Management Transport Program for HFETR
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Topics: Fuel management, Computational methods, Approximation, Errors, Geometry, Manufacturing, Neutron flux, Pressurized water reactors, Simulation
Proceedings Papers

Modeling of Cladding Thermal Evolution Along Cask Storage

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Jaime E. Penalva, Francisco Feria, Luis E. Herranz
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, V004T08A012, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30758
https://doi.org/10.1115/ICONE22-30758
View Paper titled, Modeling of Cladding Thermal Evolution Along Cask Storage
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Topics: Cladding systems (Building), Modeling, Storage, Temperature, Fuel rods, Equipment performance, Thermal characterization, Arches, Creep, Embrittlement
Proceedings Papers

Development of REFT Code System for the Analysis of Highly Heterogeneous Research Reactors

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Tengfei Zhang, Hongchun Wu, Youqi Zheng, Liangzhi Cao, Yunzhao Li
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A058, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30950
https://doi.org/10.1115/ICONE22-30950
View Paper titled, Development of REFT Code System for the Analysis of Highly Heterogeneous Research Reactors
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Topics: Fuel management, Geometry, Graphical user interfaces, Isotopes, Manufacturing, Modeling, Rods
Proceedings Papers

Neutronic Analysis and Fuel Cycle Simulation of the MIT Reactor Using MCODE-FM and Experimental Validation

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Kaichao Sun, Michael Ames, Thomas Newton, Jr., Lin-wen Hu
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T11A018, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16670
https://doi.org/10.1115/ICONE21-16670
View Paper titled, Neutronic Analysis and Fuel Cycle Simulation of the MIT Reactor Using MCODE-FM and Experimental Validation
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Topics: Nuclear fuel cycle, Simulation, Blades, Fuel management, Algorithms, Fuels, Irradiation (Radiation exposure), Neutron flux
Proceedings Papers

Neutron Absorbers in CANDU Natural Uranium Fuel Bundles to Improve Operating Margins

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Paul K. Chan, Stéphane Paquette, Hugues W. Bonin, Corey French, Aniket Pant
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A030, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15919
https://doi.org/10.1115/ICONE21-15919
View Paper titled, Neutron Absorbers in CANDU Natural Uranium Fuel Bundles to Improve Operating Margins
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Topics: Fuels, Neutrons, Uranium, Safety, Design, Neutron flux, Fuel management, Irradiation (Radiation exposure), Light water reactors, Manufacturing
Proceedings Papers

Towards Optimal In-Core Fuel Management of Thorium-Plutonium-Fuelled PWR Cores

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Nurjuanis Z. Zainuddin, Benjamin A. Lindley, Geoffrey T. Parks
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A005, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15246
https://doi.org/10.1115/ICONE21-15246
View Paper titled, Towards Optimal In-Core Fuel Management of Thorium-Plutonium-Fuelled PWR Cores
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Topics: Fuel management, Pressurized water reactors, Fuels, Cycles, Boron, Design, Materials properties, Neutrons, Radioactive wastes, Temperature
Proceedings Papers

A Study on SCWR Core Design and Fuel Management

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Yong Zhang, Jue Yang, Dongsheng Li, Liangzhi Cao, Fei Wang, Shuai Zhao, Hongbo Li
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A002, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15083
https://doi.org/10.1115/ICONE21-15083
View Paper titled, A Study on SCWR Core Design and Fuel Management
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Topics: Design, Fuel management, Supercritical water reactors, Equilibrium (Physics), Fuel rods, Temperature, Coolants, Cycles, Manufacturing, Cladding systems (Building)
Proceedings Papers

Application of Fine Depletion Calculation for LLFPs In-Core Transmutation Evaluation in PWRs

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Kun Liu, Hongchun Wu, Liangzhi Cao, Youqi Zheng, Changhui Wang
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 137-144, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54381
https://doi.org/10.1115/ICONE20-POWER2012-54381
View Paper titled, Application of Fine Depletion Calculation for LLFPs In-Core Transmutation Evaluation in PWRs
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Topics: Pressurized water reactors, Fuel management, Reliability, Stability
Proceedings Papers

Development of a Core Management Tool for MYRRHA: Work in Progress

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David Jaluvka, Gert Van den Eynde, Stefan Vandewalle
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 625-631, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54542
https://doi.org/10.1115/ICONE20-POWER2012-54542
View Paper titled, Development of a Core Management Tool for MYRRHA: Work in Progress
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Topics: Design, Education, Fuel management, Fuels, Irradiation (Radiation exposure), Machinery, Nuclear research, Optimization, Radioisotopes, Silicon
Proceedings Papers

Discussion of the Effects of AP1000 First Core Loading Pattern Design on Nuclear Power Plant Operation

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Xuesong Li
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 517-521, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30041
https://doi.org/10.1115/ICONE18-30041
View Paper titled, Discussion of the Effects of AP1000 First Core Loading Pattern Design on Nuclear Power Plant Operation
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Topics: Design, Nuclear power plant operations, Leakage, Safety, Cycles, Stress, Economic analysis, Equilibrium (Physics), Fuel management, Fuels
Proceedings Papers

Burn-Up Calibration and Error Analysis of HTR-10 Spherical Fuel Elements by Gamma Spectroscopy

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Bing Xia, Fu Li, Zongxin Wu
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 437-444, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29300
https://doi.org/10.1115/ICONE18-29300
View Paper titled, Burn-Up Calibration and Error Analysis of HTR-10 Spherical Fuel Elements by Gamma Spectroscopy
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Topics: Calibration, Error analysis, Fuels, Gamma ray spectrometry, Errors, Measurement systems, Graphite, Very high temperature reactors, Absorption, Alpha decay
Proceedings Papers

EPR™: A Reactor to Support Economical Fuel Cycles

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S. Zheng, R. Meinl, J. Stephens
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 107-112, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29439
https://doi.org/10.1115/ICONE18-29439
View Paper titled, EPR™: A Reactor to Support Economical Fuel Cycles
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Topics: Cycles, Fuels, Fuel management, Design, Economic analysis, Nuclear fuel cycle, Pressurized water reactors, Safety, Uranium
Proceedings Papers

Verification and Validation of AEGIS/SCOPE2: The State-of-the-Art In-Core Fuel Management System for PWRs

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Masahiro Tatsumi, Yasunori Ohoka, Tomohiro Endo, Naoki Sugimura, Masato Tabuchi, Hideaki Hyoudou, Tadashi Ushio, Masaaki Mori, Akio Yamamoto
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 9-15, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29154
https://doi.org/10.1115/ICONE18-29154
View Paper titled, Verification and Validation of AEGIS/SCOPE2: The State-of-the-Art In-Core Fuel Management System for PWRs
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Topics: Fuel management, Pressurized water reactors, Boron, Cross section (Physics), Geometry, Manufacturing, Stability
Proceedings Papers

PWR Fuel Management Optimization Using a New Integer Coded Genetic Algorithm

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Ahmad Zolfaghari, Hamid Minuchehr, Ali Noroozy, Peymaan Makarachi
Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 205-209, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75932
https://doi.org/10.1115/ICONE17-75932
View Paper titled, PWR Fuel Management Optimization Using a New Integer Coded Genetic Algorithm
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Topics: Fuel management, Genetic algorithms, Optimization, Pressurized water reactors, Design, Fuels