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Keywords: fast reactor
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Proceedings Papers

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A006, August 4–5, 2020
Paper No: ICONE2020-16666
... agreed well with the results provided by other participants of this CRP. Keywords: Fast reactor, EBR-II, V&V, reactivity feedback 1. INTRODUCTION Experimental Breeder Reactor II (EBR-II) was a liquid metal reactor (LMR) located in Idaho which was designed by Argonne National Laboratory (ANL). It was...
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, V002T08A006, August 4–5, 2020
Paper No: ICONE2020-16091
...STUDY ON EUTECTIC MELTING BEHAVIOR OF CONTROL ROD MATERIALS IN CORE DISRUPTIVE ACCIDENTS OF SODIUM-COOLED FAST REACTORS: (2) Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State Toshihide Takai, Tomohiro Furukawa Hidemasa Yamano Japan Atomic Energy...
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. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A011, August 4–5, 2020
Paper No: ICONE2020-16368
... fusion driven system transuranium tritium breeding ratio fast reactor Abstract The subcritical fission system could be used to transmute actinide elements from spent fuel into thermal power. Since the subcritical system needs an external neutron source, the D-T Fusion reactor was...
Proceedings Papers

Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 669-675, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54725
... System Safety Department, JNES Tokyo, JAPAN Phone:+81(3)4511-1836 shindo-yoshihisa@jnes.go.jp KEY WORDS: fast reactor, plant dynamic analysis, statistical safety analysis, flow network ABSTRACT Japan Nuclear Energy Safety Organization, JNES has been studying the methodology to apply the risk informed...
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 2, 175-180, May 17–21, 2010
Paper No: ICONE18-29547
... 08 04 2011 Metal fuelled sodium cooled fast reactors are known to have high breeding ratio and short doubling time. Due to these features they play a very important role in the energy scenario, where higher power growth is required. Large sodium cooled fast reactors have positive...
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 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition, 411-415, July 12–16, 2009
Paper No: ICONE17-75250
..., North Ward, Sapporo, Japan Phone & Fax :+81-11-706-7842 E-mail: k-sugi@eng.hokudai.ac.jp Keywords: fast reactor, liquid sodium droplet, oxidization, combustion, dendrite oxides ABSTRACT Liquid sodium is used as the coolant of the fast reactor because of its high thermal conductivity. It is superior as...
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
... and the behavior of solid reaction products in the pool was obtained to evaluate the consequences of boundary tube failure incident in a sodium-CO2 heat exchanger. fast reactor sodium carbon dioxide chemical reaction supercritical CO2 gas-turbine heat exchanger tube failure experimental...
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
... (FBTR) at Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam, is a sodium cooled, loop type fast reactor. Its main aim is to provide experience in fast reactor operation and large scale sodium handling and to serve as a test bed for irradiation of fast reactor fuels and materials. FBTR was...
Proceedings Papers

Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 909-918, July 12–16, 2009
Paper No: ICONE17-75698
... advantage of international experience and agreed to use Japan Sodium-cooled Fast Reactor (JSFR) [2] as reference for Funding Opportunity Announcement (FOA) studies [1]. Since the scale-up factor of two is acceptable increase from manufacturing and licensing points of view, INRA proposes 3 evolutions of the...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 617-620, April 14–18, 2002
Paper No: ICONE10-22231
.... Analyses are conducted with a Monte-Carlo code, MCNP. Fast reactor Burnable poison Critical experiment Gadolinium PROCEEDINGS of ICONE10: 10TH International Conference on Nuclear Engineering VIT LI In TR INC is composed of natural gadolinium oxide (Gd2O3) mixed in polyethyle without G 0.943at...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 943-949, April 14–18, 2002
Paper No: ICONE10-22524
... EBR-II sodium-cooled fast reactor metallic fuel LMR passive safety liquid-metal-cooled recycled fuel The Experimental Breeder Reactor No. 2 (EBR-II) began operation in August 1964 as an engineering test of the operation of a sodium-cooled fast reactor power plant system. Its primary...
Proceedings Papers

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 417-432, April 14–18, 2002
Paper No: ICONE10-22622
... fast reactor nitride fuel isotope separation pressure swing adsorption fuel reprocessing fuel fabrication Highly-isotopically-enriched nitrogen (HE-N 2 ; 15 N abundance ≥ 99.9%) is indispensable for a nitride fueled fast reactor (FR) cycle to minimize the effect of carbon-14 ( 14 C...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 269-274, April 25–29, 2004
Paper No: ICONE12-49076
... Hydrogen Production Sodium cooled Small reactor Fast reactor Feasibility study In phase II of a feasibility study on commercialized fast reactor cycle system of Japan Nuclear Cycle Development Institute, we are finding a concept of a multi-purpose small sized fast reactor with various...
Proceedings Papers

Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 11-16, April 25–29, 2004
Paper No: ICONE12-49151
... Carbon Dioxide Supercritical CO 2 Corrosion ATHENA Fast Reactor An experimental apparatus for the investigation of the flow-assisted corrosion of potential fuel cladding and structural materials to be used on a fast reactor cooled by supercritical carbon dioxide has been designed...
Proceedings Papers

Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 537-542, July 17–20, 2006
Paper No: ICONE14-89299
... 17 09 2008 Effects of SiC cladding and structure on neutronics of reactor core for small lead-cooled fast reactors have been investigated analytically. The fuel of this reactor was uranium nitride with 235 U enrichment of 11% in inner core and 13% in outer core. The reactors were...
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, 757-763, July 17–20, 2006
Paper No: ICONE14-89668
... Creep-fatigue Elastic follow-up Elevated temperature design Fast reactor JSME Since its foundation in 1997, the Main Committee on Power Generation Facility Codes, MC-PGFC, of the Japan Society of Mechanical Engineers, JSME, has issued a number of nuclear codes including the rules on...