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Keywords: PWR
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Proceedings Papers

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A100, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92637
... 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. Keywords: Control rod position monitoring; Global search algorithm; PWR; 1. INTRODUCTION Place the introduction here. All running text, including...
Proceedings Papers

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
...Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-93049 STUDY ON PASSIVE PULSE COOLING METHOD OF SECONDARY SIDE IN PWR NUCLEAR POWER PLANT Zhenhua Wu Suzhou Nuclear Power Research Institute Co.,Ltd. Shenzhen, China Junjun...
Proceedings Papers

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

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
... fuel cycle PWR fast reactor hybrid MOX Abstract China implements the established policy of closed nuclear fuel cycle for the sustainable development of nuclear power. However, there seems no feasible development plan and roadmap to initiate and deploy a commercial closed fuel cycle...
Proceedings Papers

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
... PWR spent fuel dry storage loading pattern safety evaluation operating experience 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...
Proceedings Papers

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

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
... Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-61090 RADIATION DOSE EVALUATION OF TYPICAL DESIGN BASIS ACCIDENT FOR ADVANCED PWR IN CHINA Haiying Chen, Shaowei Wang, Xinlu Tian*, Fudong Liu Nuclear and Radiation Safety Center, Ministry of Ecology and Environment, Beijing, China ABSTRACT...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A076, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65663
... transient analysis reactor safety PWR LOCA SGTR PCTRAN Abstract The impact of nuclear accidents has been a topic of debate since the construction of the first nuclear reactor, and still stands as a key issue of public concern. Several codes and simulators have been used to study...
Proceedings Papers

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
... and will generalize 3D-multiphysics coupling, performing benchmark against current industrial codes used for comprehensive safety assessment) is a three years project PWR and VVER safety assessment. CAMIVVER will launched under the European Union research program demonstrate CFD assets and compatibility...
Proceedings Papers

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
...: Climatic Hazards, Climate Change, Safety, PWR 1. INTRODUCTION According to the Periodic Safety Review Process, the safety level of EDF s Pressurized Water Reactors is re-assessed every ten years, considering national and international operational feedback, evolution of knowledge and best available...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A012, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16136
... (Nuclear Power Plant) site, in order to verify if the protection measures are sufficient or, if necessary, to design adequate protection. To cope with those objectives, wind flow behavior around a PWR (Pressurized Water Reactor) nuclear power plant is studied. The goal of this work is to check...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A022, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16187
.... In conclusion, the capacity of the EDF 900 MW NPPs to cope with high level of natural hazard (equivalent to decamillennial events) is being verified through the 4 th periodic safety reviews, in compliance with WENRA reference level T4.2. natural hazards WENRA DBH safety PWR PROTECTION OF NUCLEAR...
Proceedings Papers

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, V001T05A015, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16872
... PWR control rod stress strain FEA Abstract This work aims to develop a finite element model of a PWR control rod at operating conditions for stress analysis of the rod cladding. The finite element model simulates a control rod exposed to high operating temperatures and pressure while...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A009, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16761
... pressurized water reactor (PWR) under the following accident scenarios: station blackout (SBO), loss of feedwater (LOFW), steam generator tube rupture (SGTR), loss-of-coolant accidents (LOCAs), locked rotor transient, turbine trip transient, anticipated transient without scram (ATWS), and main steam line...
Proceedings Papers

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, V001T05A012, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16674
... PWR fuel cladding PCMI Abstract Pellet-Cladding Mechanical Interaction (PCMI) failure is the one of failure mode which must be evaluated in the nuclear fuel safety. PCMI is caused by the mechanical load to cladding due to the fuel pellet expansion. Under the high fuel burnup condition...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A051, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16927
...MODELING THE FLOW REDISTRIBUTION UPSTREAM FROM THE SPACER GRID OF A PWR Stanislas de Lambert1, Jérome Cardolaccia Université Paris-Saclay, CEA, Service d'études mécaniques et thermiques, 91191, Gif-sur-Yvette, France Vincent Faucher CEA, IRESNE, Département de Technologie Nucléaire, 13108, Saint...
Proceedings Papers

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

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, V005T11A003, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15275
... TRISO coated particle, developed for HTGR initially, has advantages of nuclear proliferation-resistance and fuel integrity against the release of fission products. In this paper, a 350MWt small sized PWR core design utilizing TRISO fuel concept is presented. TRISO particles are dispersed...
Proceedings Papers

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, V005T11A007, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15714
... The mechanisms of the radionuclide 14 C production and releasing from pressurized water reactor (PWR) nuclear power plant (NPP) are simply described in the paper. The yield calculation model for 14 C produced in PWR is offered in this work. The averaged neutron flux in reactor core under...
Proceedings Papers

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, V005T13A024, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16322
... Camera elevator is the dominating device of the manipulator crane closed circuit TV system which is used in under constructing domestic PWR in China. The manipulator operator can use camera elevator to view refueling operation (insertion and withdrawal) and other underwater condition...