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Keywords: Containment
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Proceedings Papers
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A058, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135097
... Abstract After a serious accident in the PWR nuclear power station, the radioactive aerosol will be released into the containment with the steam from the reactor core. Due to the huge volume of the containment itself, the mixture of steam, air and other gases and fission products may form...
Proceedings Papers
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A031, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135418
... Abstract The containment of the nuclear power plant is an important item of the tolerance nuclear steam supply system. It is the third barrier to prevent radioactive waste from leakage after an accident. It is the most important structure of nuclear power plant ensuring the safety of nuclear...
Proceedings Papers
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A043, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92477
... Abstract The prestressed containment structure is the last physical barrier against the spread of radioactive material. In addition to being able to resist the pressure caused by internal accidents, it should also have a certain ability to resist external projectiles or explosive shocks. Under...
Proceedings Papers
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92842
... Abstract Filtered containment venting system (FCVS) is used in some nuclear power plants to avoid containment overpressure failure and uncontrolled radioactive release in severe accidents. Currently the opening strategy is mainly based on the containment pressure, such as the design pressure...
Proceedings Papers
Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A004, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89165
... Abstract As the main coolant piping from the steam generator to the reactor pressure vessel, cold leg is an important part of the primary circuit. During a LOCA accident in the cold leg, the parameter sensitivity has a crucial influence for the containment response. PAREO program is used...
Proceedings Papers
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A055, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92955
... and thermophoresis effect. Once a water-ingress accident occurs, the graphite dust may resuspend due to the rapid change of flow field. A certain fraction of resuspended dust, together with some fission products, could be discharged to the containment if the overpressure protection of the primary circuit...
Proceedings Papers
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A014, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91532
...Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-91532 NUMERICAL STUDY ON THERMAL HYDRAULIC CHARACTERISTICS OF CONTAINMENT SPRAYING EXPERIMENT IN COHERE FACILITY Junying Xu China Nuclear Power Technology Research...
Proceedings Papers
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A026, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92404
... formula was reduced by 82.80% and 82.31%, respectively. Keywords:Wet Radioactive Waste; Cement curing; Containment; Compressive Strength;leaching rate. NOMENCLATURE alpha beta gama 1. INTRODUCTION The original Westinghouse cement solidification formula is the formula complementary to the radioactive...
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, V003T12A021, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64403
... Abstract After the Fukushima accident, the disposal of radioactive liquid waste has received great attention. The analysis of nuclide activity in the liquid waste of the containment after a severe accident is the prerequisite for the treatment of the liquid waste. Based on the source...
Proceedings Papers
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A028, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15885
... ABSTRACT In order to study the mechanism of mixed-convection and heat transfer when injecting hot water vapor into the containment, it is necessary to measure temperature distribution inside it. To overcome the shortcomings of traditional thermocouples technique during injection experiments of water vapor...
Proceedings Papers
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A066, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15946
... 1 Copyright © 2013 by ASME NUMERICAL ANALYSIS OF CONTAINMENT RESPONSE UNDER ACCIDENT CONDITIONS Shengzhi Yu College of Nuclear Science and Technology, Harbin Engineering University Harbin, Heilongjiang, China Jianjun Wang College of Nuclear Science and Technology, Harbin Engineering University...
Proceedings Papers
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A004, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15241
... Prestressed reinforced concrete containment is an important part among the safety-related buildings, and the presressing technology is widely used in containment construction which is best suited to the cylindrical-type containment topped by a dome. It has been recognized that traditional...
Proceedings Papers
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A068, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15960
... Containment Passive Closed loop In this paper, a closed loop concept, which is composed of two heat exchangers with same scale, pipes, valves and one tank, has been developed as a passive containment cooling system for a large dry concrete containment. The system is designed to maintain...
Proceedings Papers
Gerhard Poss, Teja Kanzleiter, Friedhelm Funke, Gert Langrock, Hans-Josef Allelein, Holger Nowack, Gunter Weber
Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 721-726, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48692
... Passive Autocatalytic Recombiners (PARs) in PWR-Containments remove hydrogen released in case of a severe accident with core damage by catalytic oxidation with the oxygen of the containment atmosphere. The removal of hydrogen in autocatalytic recombiners (PARs) results in temperature levels...
Proceedings Papers
Proc. ASME. ICONE16, Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 1069-1076, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48953
... We address in this paper the case of a new generation PWR NPPs, which containment is equipped with a metallic liner on the inner face, in order to minimise leakage. A net of angles that, in addition to studs, constitute the anchoring system to the concrete, strengthens this metallic liner, also...
Proceedings Papers
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 681-695, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48550
... During the course of a hypothetical accident in a nuclear power plant, spray might be activated in order to reduce static pressure in the containment. To have a better understanding of the heat and mass transfers between a spray and the surrounding confined gas, the IRSN has developed the TOSQAN...
Proceedings Papers
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 707-716, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48582
... TOSQAN is an experimental program undertaken by the Institut de Radioprotection et de Suˆrete´ Nucle´aire (IRSN) in order to perform thermal hydraulic containment studies. The TOSQAN facility is a large enclosure devoted to simulate typical accidental thermal hydraulic flow conditions in nuclear...
Proceedings Papers
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 785-795, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22394
... 05 03 2009 A method for provision of containment integrity and localizing capability of the new generation NPPs with WWER reactor units under the beyond design accidents is discussed. The aim is achieved by equipment of NPPs by additional passive systems. New generation NPP...
Proceedings Papers
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 1041-1055, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22661
... containment thermal hydraulics accident The MISTRA facility is a large scale experiment, designed for the validation of thermal-hydraulics multi-D codes. A short description of the facility, the set up of the instrumentation and the test program are presented. Then, experimental results...
Proceedings Papers
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 137-144, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22206
...1pressure and high temperature. A study has been carried out using the GASFLOW 2.1 three-dimensional CFD code to evaluate the hydrogen distribution in the containment during a beyond design basis accident. The VVER-440/213 cts. One 3D block contains the reactor buildi ls the air traps. 1D ducts...
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