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Keywords: containment
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Proceedings Papers

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
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
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
Paper No: ICONE29-91532
... Abstract The containment spray system is designed to control the pressure rise and avoid overpressure risk by condensing the steam in severe accidents. To study the containment thermal-hydraulic response characteristics after spraying, the spray experiment has been performed in COHERE facility...
Proceedings Papers

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A026, August 8–12, 2022
Paper No: ICONE29-92404
... formula was reduced by 82.80% and 82.31%, respectively. wet radioactive waste cement curing containment compressive strength leaching rate Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-92404 STUDY ON IMPROVEMENT...
Proceedings Papers

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A019, August 8–12, 2022
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

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A043, August 8–12, 2022
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. 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
Paper No: ICONE28-64403
...Abstract 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 4: Thermal Hydraulics, V004T09A066, July 29–August 2, 2013
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 4: Thermal Hydraulics, V004T09A068, July 29–August 2, 2013
Paper No: ICONE21-15960
...1 Copyright © 2013 by ASME STUDY ON THE BEHAVIORS OF A CONCEPTUAL PASSIVE CONTAINMENT COOLING SYSTEM Jianjun Wang Harbin Engineering University Harbin, HeiLongjiang, China Beibei Luo Harbin Engineering University Harbin, HeiLongjiang, China Xueqing Guo Harbin Engineering University Harbin...
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
Paper No: ICONE21-15241
... STUDY ON THE PRESTRESSING EFFECT IN REINFORCED CONCRETE CONTAINMENT BY USING ANSYS SUN Feng Nuclear and Radiation Safety Center of MEP Beijing of China PAN Rong Nuclear and Radiation Safety Center of MEP Beijing of China ABSTRACT Prestressed reinforced concrete containment is an important part...
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
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. 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
Paper No: ICONE16-48953
... 09 07 2009 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...
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
Paper No: ICONE16-48550
... 09 07 2009 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...
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
Paper No: ICONE16-48582
... 09 07 2009 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...
Proceedings Papers

Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 721-726, May 11–15, 2008
Paper No: ICONE16-48692
... 09 07 2009 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...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 137-144, April 14–18, 2002
Paper No: ICONE10-22206
... Hydrogen combustion may represent a threat to containment integrity in a VVER-440/213 plant owing to the combination of high pressure 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...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 785-795, April 14–18, 2002
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
Paper No: ICONE10-22661
... measurements.Thecontainmentispreheatedby steamcondensationandinsulatedwithrockwool. Thethreecondensers: Threecondensersareinsertedinsidethe containment,enlargedtothecontainment diameter.Eachcondenserhasitsownregulation circuit.Thisisspeciallydesignedtoensurethe moststableanduniformwalltemperature:the maximumoutside...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 627-632, April 25–29, 2004
Paper No: ICONE12-49428
... 25 11 2008 In 2004, a new Code Case, N-717, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) will be published. The new Code Case provides rules for construction of containments used for storage of spent nuclear fuel and high level...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 829-835, April 25–29, 2004
Paper No: ICONE12-49533
... 25 11 2008 Three experiments on containment phenomena, which were performed in the TOSQAN, PHEBUS and KAEVER integral experimental facilities, were simulated with the lumped-parameter computer code CONTAIN. In the experiments, which were performed at similar pressure and temperature...