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Keywords: FBR
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Proceedings Papers

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A046, August 4–5, 2020
Paper No: ICONE2020-16796
... Ibaraki, Japan Jun Kobayashi Japan Atomic Energy Agency Ibaraki, Japan Akikazu Kurihara Japan Atomic Energy Agency Ibaraki, Japan Yasuhiro Miyake NDD Ibaraki, Japan Keywords: FBR, Natural circulation flow field, PIV ABSTRACT In Sodium-cooled Fast Reactors (SFRs), it is important to optimize the design...
Proceedings Papers

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A037, August 4–5, 2020
Paper No: ICONE2020-16679
... the wrapping wire were conducted. From the results, the effect of the wrapping wire on the flow field in the subchannel was understood. There experimental results useful not only for understanding of pin bundle thermal hydraulics but also code validation. FBR wire wrapped pin bundle subchannel PIV...
Proceedings Papers

Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T15A008, July 29–August 2, 2013
Paper No: ICONE21-15633
...-1 Tennoudai, Tsukuba, Ibaraki, 305-8573, Japan Phone: +81-29-853-5487 Fax: +81-29-853-5487 Email: tkuroda1215@gmail.com Eiji MATSUO Mitsubishi FBR Systems, Inc. 2-34-17 Jingumae, Shibuya-ku, Tokyo, 150-0001,Japan Phone: +81-3-6439-4333 Fax: +81-3-6439-4399 Email: eiji_matuo@mfbr.mhi.co.jp Kenichi...
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, V005T11A019, July 29–August 2, 2013
Paper No: ICONE21-16707
... A new FBR lattice physics code GALAXY-H has been developed by Mitsubishi Heavy Industries, Ltd. (MHI). GALAXY-H is a hexagonal version of GALAXY, which is a two dimensional transport calculation code for PWR assembly. GALAXY-H generates assembly nuclear constants used in the FBR core calculation...
Proceedings Papers

Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 299-308, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54404
... data. FBR Wire Wrapped Pin Bundle Subchannel PIV Investigation on Velocity Distribution around the Wrapping Wire in an Inner Subchannel of Fuel Pin Bundle Masahiro Nishimura Oarai Research and Development Center Japan Atomic Energy Agency 4002 Narita, O-arai, Ibaraki 311-1393, Japan Phone...
Topics: Fuels, Wire
Proceedings Papers

Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 175-184, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54412
... When a hypothetical Core Disruptive Accident (CDA) occurs in Fast Breeder Reactor (FBR), it is strongly required that the molten core material can be solidified and cooled down by the sodium coolant in a reactor vessel. In order to estimate whether the molten material jet is completely...
Topics: Solidification
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, 479-484, May 11–15, 2008
Paper No: ICONE16-48880
... 09 07 2009 We proposed the “Flexible Fuel Cycle Initiative” (FFCI), which has flexibility for the uncertainties like the introduction speed of FBRs. On the other hand, during the FBR introduction period, Pu from LWR spent fuel is used for startup of FBRs. But the FBR core being loaded...
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, 955-960, May 11–15, 2008
Paper No: ICONE16-48768
... and this leads monotonous distribution of void fraction in the sodium pool. FBR Steam generator Sodium-water reaction Void fraction Proceedings of the 16th International Conference on Nuclear Engineering ICONE16 May 11-15, 2008, Orlando, Florida, USA 1 Copyright © 2008 by ASME Phone & Fax :+81-11-706...
Proceedings Papers

Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 579-588, May 11–15, 2008
Paper No: ICONE16-48578
... 09 07 2009 In order to develop a thermal-hydraulic analysis model of the SG (steam-generator) to simulate transient phenomena in the FBR (sodium cooled fast breeder reactor) MONJU, JNES (Japan Nuclear Energy Safety Organization) validated a SG analysis model using the RELAP5/3D code...
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
... 09 07 2009 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 idea is that nano-meter size particles...
Proceedings Papers

Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 217-224, July 17–20, 2006
Paper No: ICONE14-89458
.... A real scale test is considered as an accurate method to evaluate the occurrence of the vortex type GE, but the real scale test is generally expensive and not useful in the design study of large and complicated FBR systems, because frequent displacement of inner equipments accompanied by the design...
Proceedings Papers

Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 437-445, July 17–20, 2006
Paper No: ICONE14-89421
... In order to develop a thermal-hydraulic model of the steam-generator (SG) to simulate transient phenomena in the sodium cooled fast breeder reactor (FBR) MONJU, Japan Nuclear Energy Safety Organization (JNES) verified the SG model using the RELAP5/MOD3 code against the results of the turbine...
Proceedings Papers

Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 555-563, July 17–20, 2006
Paper No: ICONE14-89234
... It is important to estimate the cooling possibility of the molten jet in coolant during a core disruptive accident (CDA) of a fast breeder reactor (FBR). In the present study, the molten jet of U-alloy 78 simulating the core material is injected into the water simulating the coolant. The visual...