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Keywords: Sodium
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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, V001T02A003, August 4–5, 2020
Paper No: ICONE2020-16735
... inspection rationalization risk informed constraint condition fast reactor primary piping sodium Abstract In order to rationalize maintenance for nuclear power plants, it is necessary to develop optimize maintenance plan by considering characteristics of each plant. In sodium-cooled...
Proceedings Papers

Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 185-189, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54454
... SURFACE TENSION OF LIQUID SODIUM WITH SUSPENDED NANOPARTICLES Takuro OGAWA Ken-ichiro SUGIYAMA Hokkaido University, North13 West8, North Ward, Sapporo, Japan Phone&Fax : +81-11-706-7842, E-mail: ogawa.takuro_0202@eng.hokudai.ac.jp Keyword: Sodium-cooled fast reactor, Sodium, Nano particles...
Proceedings Papers

Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 359-366, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54505
... fast reactor sodium corrosion products corrosion hazard evaluation code JOYO Radioactive corrosion products (CPs) are a main cause of personal radiation exposure during maintenance with no breached fuel in sodium-cooled fast breeder reactor (FBR) plants. In order to establish...
Proceedings Papers

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 71-78, May 17–21, 2010
Paper No: ICONE18-29171
... fast reactor sodium corrosion products corrosion hazard evaluation code MONJU Radioactive corrosion products (CP) are main cause of personal radiation exposure during maintenance with no breached fuel in FBR plants. CP is produced in the core region by activation of fuel cladding and...
Proceedings Papers

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 65-70, May 17–21, 2010
Paper No: ICONE18-29169
... fast reactor sodium volatile fission product vaporization partition coefficient activity coefficient experimental study Equilibrium partition coefficients were experimentally measured for volatile fission products of cesium and iodine between liquid sodium pool and the inert cover...
Proceedings Papers

Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 709-716, July 12–16, 2009
Paper No: ICONE17-75900
... 23 02 2010 Reaction behavior of carbon dioxide (CO2) with a liquid sodium pool was experimentally investigated to understand the consequences of boundary tube failure in a sodium-CO2 heat exchanger. In this study, two kinds of experiments were carried out to investigate the reaction...
Proceedings Papers

Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 803-811, July 12–16, 2009
Paper No: ICONE17-75131
... 23 02 2010 In the framework of PSI’s FAST code system, the TRACE thermal-hydraulics code is being extended for representation of sodium two-phase flow. As the currently available version (v.5) is limited to the simulation of only single-phase sodium flow, its applicability range is not...
Proceedings Papers

Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 893-898, July 12–16, 2009
Paper No: ICONE17-75592
... 23 02 2010 Sodium cooled fast breeder reactors constitute the second stage of India’s three-stage nuclear energy programme, for effective utilization of the country’s limited reserves of natural uranium and exploitation of its large reserves of thorium. The Fast Breeder Test Reactor...
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, 559-563, May 11–15, 2008
Paper No: ICONE16-48367
...: Sodium, Chemical reactivity, FBR, Nano-particle, Nano-fluid ABSTRACT Liquid sodium is used as the coolant of the fast breeder reactor (FBR). A weak point of sodium is a high chemical reactivity with water or oxygen. So an idea of chemical reactivity suppression of liquid sodium itself is proposed. The...
Proceedings Papers

Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 961-965, May 11–15, 2008
Paper No: ICONE16-48788
... very limited. The measurement was done in a sealed box keeping inert gas atmosphere, which is required for sodium experiment because of an easy chemical reaction of sodium with oxygen and moisture. At first, we did a series of experiments for pure sodium. We succeeded to make pendant drops between 150...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 311-317, April 14–18, 2002
Paper No: ICONE10-22211
...1th e s -1 ta 2600Pa to 0.12Mpa. Not only the mechanism of the instability, critical conditions and oscillation period, but also the effects of p w F te f f o e K D 1. INTRODUCTION The research on the instability of liquid sodium boiling two-phase flow is of great importance for the safety...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 857-865, April 14–18, 2002
Paper No: ICONE10-22462
... EBR-II closure sodium deactivation LMFBR The Department of Energy mandated the termination of the Integral Fast Reactor (IFR) Program, effective October 1, 1994. To comply with this decision, Argonne National Laboratory-West (ANL-W) prepared a plan providing detailed requirements to...
Proceedings Papers

Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 531-537, July 17–20, 2006
Paper No: ICONE14-89398
... 17 09 2008 The experimental study has been carried out to investigate reaction, transport and settling behavior of lead-bismuth eutectic (LBE) in flowing liquid sodium. In the test, 168g of LBE were poured into flowing sodium from the top of a vertical-type sodium loop which contained...
Topics: Sodium