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Keywords: PWR
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Proceedings Papers

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A010, August 4–6, 2021
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. 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
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
Paper No: ICONE28-61090
... Proceedings of the 2021 28th International Conference on Nuclear 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...
Proceedings Papers

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A076, August 4–6, 2021
Paper No: ICONE28-65663
... the transient progression in pressurized on the safety of reactors in general, and PWR in water reactors, and to evaluate the technical particular. This has also spurred novel research in measures adopted to scale down the risk of accidents. advanced, passive safety systems to further improve However, some...
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
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. 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
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
Paper No: ICONE2020-16136
... 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 that there is no exceeding local wind speed relative to the wind entering the site. The severe winds are characterized locally near the buildings in terms...
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
Paper No: ICONE2020-16187
..., 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 4th periodic safety reviews, in compliance with WENRA reference level T4.2. Keywords: Natural Hazards, WENRA, DBH, Safety, PWR Copyright © 2020 ASME ICONE2020-16187...
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
Paper No: ICONE2020-16872
...STRESS ANALYSIS OF THE PRESSURIZED-WATER REACTOR CONTROL ROD UNDER OPERATING CONDITIONS Leo A. Carrilho Westinghouse Electric Company, Columbia, SC 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...
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
Paper No: ICONE2020-16761
... the risk impacts from near-term ATF (FeCrAl and Chromium-coated clads) on a generic Westinghouse three-loop 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...
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
Paper No: ICONE2020-16674
... of this code is validated using the experimental test data. PWR fuel cladding PCMI DEVELOPMENT OF THE FUEL BEHAVIOR ANALYSIS CODE FOR MECHANICAL FUEL CLADDING FAILURE DURING REACTIVITY INSERTION EVENT IN PWR Yuma Higashi 1 , Nozomu Murakami 1 , Tadakatsu Yodo 1 , Teruhisa Yamamoto 2 1 Mitsubishi...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A051, August 4–5, 2020
Paper No: ICONE2020-16927
.... The approach has been validated with both CFD simulations and an experimental mock-up. spacer grids PWR hydraulic network fuel assemblies’ deformation MODELING THE FLOW REDISTRIBUTION UPSTREAM FROM THE SPACER GRID OF A PWR Stanislas de Lambert1, Jérome Cardolaccia Université Paris-Saclay, CEA...
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
Paper No: ICONE21-15275
... REACTIVITY HOLD-DOWN TECHNIQUE FOR A SOLUBLE BORON FREE PWR USING TRISO PARTICLE FUEL Xiang Dai, Xinrong Cao* College of Nuclear Science and Technology, Harbin Engineering University, Harbin, Heilongjiang, 150001, China Tel86)451 82518692 Fax86)45182518692 E-mail:caoxinrong@hrbeu.edu.cn ABSTRACT...
Proceedings Papers

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, V001T01A008, July 29–August 2, 2013
Paper No: ICONE21-15099
... According to advanced light water reactor (ALWR) Utility Requirement Document (URD), plant control systems should be designed to meet the specified design requirements for an advanced 1000 MWe class PWR nuclear power plant (NPP). As per the plant design requirements, AP1000 control systems were...
Proceedings Papers

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A087, July 29–August 2, 2013
Paper No: ICONE21-16354
... AP1000 3D ROD EJECTION REACTOR CORE THERMAL ANALYSES QIN Huimin Shanghai Nuclear Engineering Research & Design Institute (SNERDI) 29 Hong Cao Rd., Shanghai 200233, China Tel: +86-21-61861158, Fax: +86-21-61860728, E-mail: qinhuimin@snerdi.com.cn Key Words: PWR, Rod Ejection, three dimensional...
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
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
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...
Proceedings Papers

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A025, July 29–August 2, 2013
Paper No: ICONE21-16810
... An introduction to RCC-C, an AFCEN Code for Design and Construction of PWR Fuel Assemblies Christine VAUGLIN RCC-C Editorial Group Chairman AREVA NP Fuel 10 rue Juliette Récamier 69456 LYON - FRANCE Phone: +33 (0) 472 748 064 christine.vauglin@areva.com Marc TON-THAT RCC-C Subcommittee Chairman...
Proceedings Papers

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T10A032, July 29–August 2, 2013
Paper No: ICONE21-15929
... Flow distribution at core inlet is an important criteria of reactor hydraulic performance, affected by flow distribution device. Compared with the Generation II PWR, the AP1000 flow distribution device has a great changed, it depends on the flow skirt. In order to strengthen understanding...
Proceedings Papers

Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 381-386, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54670
... In order to research the performance of Pressurized Water Reactor (PWR) with 1/3 MOX fuel in the initial cycle, this paper serves Qinshan II reactor core as the reference core to design suitable MOX assemblies and study relevant core properties. The analyses documented within use assembly cross...