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Keywords: PWR
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Proceedings Papers
Bamboo-Frame: An Automatic Modeling Tool for the Two-Step Reactor Core Physics Analysis
Available to PurchaseYuancheng Zhou, Yunzhao Li, Yisong Li, Yilin Liang, Hengrui Zhang, Shilong Zhou, Weiguo Wang, Yuxiang Ou
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A038, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135358
... to be complex and error-prone. In light of this, we developed Bamboo-Frame to automate the modeling procedure in Pressurized Water Reactor (PWR) core analysis. This innovative tool requires users to provide only structural and operational parameters, while effectively managing complex tasks such as lattice...
Proceedings Papers
Establish and Analysis of an Optimized System for Hydrogen Production From Nuclear Energy in China
Available to Purchase
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130730
... higher than that of other hydrogen production methods coupled with PWR. The hydrogen production efficiency of this method can be higher than 42%, which is more than 50% higher than that before optimization. The comparison of the hydrogen production efficiency of this method with that of other renewable...
Proceedings Papers
Discussion on Radiation Protection for PWR Second-Loop Steam Supply Outside for Industrial Application
Available to Purchase
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134481
...Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August 4-8, 2024, Prague, Czech Republic ICONE31-134481 DISCUSSION ON RADIATION PROTECTION FOR PWR SECOND-LOOP STEAM SUPPLY OUTSIDE FOR INDUSTRIAL APPLICATION Yaping Zhuang Shandong Nuclear Power Company, Haiyang...
Proceedings Papers
Validation of TRACE Simulation of Small-Break LOCA Test (SB-CL-18) in the Large-Scale Test Facility
Available to Purchase
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A036, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134596
.... To demonstrate that these calculations using the simulation code are valid, it is important to validate both the simulation code and the input data. We present our approach to PWR accident analysis based on simulations of a small-break LOCA test (SB-CL-18) in the Large-Scale Test Facility (LSTF) using the three...
Proceedings Papers
CFD Analysis of a Four-Loop Pressurized Water Reactor With Multiple Operating Conditions
Available to Purchase
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134682
... inlet and outlet under asymmetric loop flow conditions are summarised, which provides certain reference value for the optimal design and safety analysis of the reactor. Keywords PWR; RPV; CFD; Porous media core; Core inlet flow distribution; Coolant flow mixing; Konvoi 1 Copyright © 2024 by ASME 1...
Proceedings Papers
Evaluation of Coolant Mixing Characteristics in the Lower Plenum of a Scaled PWR With OpenFOAM
Available to Purchase
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A009, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134558
... Abstract In the realm of nuclear reactor design, ensuring uniform flow rates at the core inlet of Pressurized Water Reactors (PWR) is vital for safety, impacting cooling functions and “fuel hot spot” criteria. This intricate balance is influenced by fluid dynamics in the reactor pressure...
Proceedings Papers
Fluid-Structure Coupling Analysis of U-Type Tube Bundle in PWR Steam Generator
Available to Purchase
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A017, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134975
... affecting tube deformation. PWR steam generator fluid-structure coupling flow induced vibration Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August 4-8, 2024, Prague, Czech Republic ICONE31-134975 FLUID-STRUCTURE COUPLING ANALYSIS OF U-TYPE TUBE BUNDLE...
Proceedings Papers
Performance Analysis for Enhanced Cr-Coated Fuel Cladding System in APR-1400 Reactor
Available to Purchase
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A049, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135127
...-of-coolant accidents. accident tolerant fuels neutronics PWR chromium coating Serpent 2.31 code Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August 4-8, 2024, Prague, Czech Republic ICONE31-135127 PERFORMANCE ANALYSIS FOR ENHANCED CR-COATED FUEL CLADDING...
Proceedings Papers
Neutronics Research on Annular Axial-Non-Uniform Minor Actinides Transmutation Targets in Commercial Pressurized Water Reactor
Available to Purchase
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A036, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135114
... of Nuclear Science and Technology, Southwest University of Science and Technology, Mianyang, China ABSTRACT This paper introduces the thermal-fast neutron conversion material 6LiD to improve the transmutation efficiency of MAs in commercial PWR, especially the fission rate, and investigate the feasibility...
Topics:
Pressurized water reactors
Proceedings Papers
Research on Scenarios and Development Paths of China’s Commercial Closed Nuclear Fuel Cycle
Available to Purchase
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A007, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89223
... of the nuclear fuel cycle requires gradual and phased progresses. Since most of the operating nuclear power plants in China are PWR units, and China implements and promotes a commercial closed nuclear fuel cycle, how to initiate a closed nuclear fuel cycle from the mature commercial pressurized water reactors...
Proceedings Papers
PWR Spent Fuel Dry Storage Loading Pattern and Safety Evaluation
Available to Purchase
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A078, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93351
... Abstract This paper describes the loading pattern, safety evaluation and operating experiences of PWR plant off-site Spent Fuel Dry Storage System (SFDSS). According to the limits from the SFDSS criticality and heat-transfer safety analysis, ALARA principle and AFA series fuel characteristics...
Proceedings Papers
Determination of Control Rod Position by Global Optimization Methods
Available to Purchase
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A100, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92637
..., the responses of the detectors to some remote rods are not obvious, which are not easy to determine. All the methods were tested on the numerical calculation examples of a pressurized water reactor case. control rod position monitoring global search algorithm PWR Proceedings of the 2022 29th...
Proceedings Papers
Performance Evaluation of Typical 3-Loop PWR With Annular Fuel Assemblies Under Typical Accidents
Available to Purchase
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A067, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92118
... of the core loaded with annular fuel by 50%. annular fuel PWR safety analysis Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-92118 PERFORMANCE EVALUATION OF TYPICAL 3-LOOP PWR WITH ANNULAR FUEL ASSEMBLIES UNDER TYPICAL...
Proceedings Papers
Study on Passive Pulse Cooling Method of Secondary Side in PWR Nuclear Power Plant
Available to Purchase
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93049
... Abstract Currently, the supplementary strategy of PWR nuclear power unit to deal with the Station Black-Out (SBO) and Total Loss of Feed-water (TLFW) accidents mainly depends on mobile facilities and manual operation. Under the SBO together with TLFW (SBO+TLFW) beyond design basis accident...
Proceedings Papers
Codes and Methods Improvements for VVER Comprehensive Safety Assessment: The CAMIVVER H2020 Project
Available to PurchaseDenis Verrier, Barbara Vezzoni, Barbara Calgaro, Olivier Bernard, Alberto Previti, Clément Lafaurie, Artur Hashymov, Pavlin Groudev, Antoaneta Stefanova, Neli Zaharieva, Frédéric Damian, Pietro Mosca, Daniele Tomatis, Ulrich Bieder, Adrien Willien, Nicolas Dos Santos, Luigi Mercatali, Victor Hugo Sanchez-Espinoza, Nicola Forgione, Sandro Paci
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A010, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64169
... comprehension of PWR and VVER. 3) European codes and methods development for VVER safety assessment will open the VVER market to the European nuclear industry. CAMIVVER will perform developments required for the new generation codes and will generalize 3D-multiphysics coupling, performing benchmark against...
Proceedings Papers
Application of Best-Estimate Plus Uncertainty Analysis Method in Nuclear Safety Evaluation
Available to Purchase
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A002, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64393
... analysis method nuclear safety evaluation PWR Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-64393 APPLICATION OF BEST-ESTIMATE PLUS UNCERTAINTY ANALYSIS METHOD IN NUCLEAR SAFETY EVALUATION Xinlu Tian, Jianping Jing...
Proceedings Papers
Radiation Dose Evaluation of Typical Design Basis Accident for Advanced PWR in China
Available to Purchase
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A004, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-61090
... than 10 15 Bq. Inhalation dose was the major contribution to the total effective dose. The total effective dose and thyroid dose of Hualong 1 at EAB and the outer boundary of LPZ fully met the requirements of Chinese GB6249. radioactivity radiation dose loss of coolant accident PWR...
Proceedings Papers
A Systematic Review of PCTRAN-Based Pressurized Water Reactor Transient Analysis
Available to Purchase
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A076, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65663
... better utilization for research and training, especially in nuclear newcomer countries. transient analysis reactor safety PWR LOCA SGTR PCTRAN Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-65663 A SYSTEMATIC...
Proceedings Papers
Protection of Nuclear Power Plants Against Natural Hazards: Protection Principles Against Rare and Severe Natural Hazards for New Nuclear Power Plants
Available to Purchase
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A002, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16185
... the French and UK regulatory contexts. Keywords: BDB, DEH, Rare and Severe Natural Hazards, Safety, PWR 1. INTRODUCTION The field of protection against external natural hazards has regularly evolved since the design of the first NPPs (Nuclear Power Plants) to take into account: operational feedback...
Proceedings Papers
Impact of Climate Change on EDF’s Nuclear Facilities: Climate Watch Approach
Available to Purchase
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A021, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16186
... of nuclear power plants to the climatic hazards through the consideration of the updated hazard levels. climatic hazards climate change safety PWR IMPACT OF CLIMATE CHANGE ON EDF'S NUCLEAR FACILITIES: CLIMATE WATCH APPROACH L. Guinard1, S. Parey2, H. Cordier1, L. Grammosenis1 1Electricité de...
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