Visualization of B4C/SS Eutectic Reaction and Liquefaction for Code development & validation
|
|
- Timothy Boyd
- 6 years ago
- Views:
Transcription
1 Visualization of B4C/SS Eutectic Reaction and Liquefaction for Code development & validation May Shota UEDA, Hiroshi MADOKORO, Byeongnam JO, Masahiro KONDO, Koji OKAMOTO Department of Nuclear Engineering and Management The University of Tokyo
2 Contents 1. Introduction 2. Experimental setup 3. Visualization experiments 4. Results 5. Conclusion 19/05/2015 2
3 Introduction
4 Background Fukushima Daiichi Simulation results of Fukushima Daiichi accident reported by TEPCO. The complete failure of the control blades probably happened in the rather early phase of the Fukushima accident. To prevent the recurrence of the severe accident and enhance its safety, clarifing the failure mechanism of control blades is really important. 19/05/2015 4
5 Absorber material in BWR[1][2] BWR fuel Control blade Absorber rod B 4 C powder Stainless Steel BWR uses B 4 C as the absorber material B 4 C is filled in the stainless steel tube Stainless steel tubes are installed in control blade 5
6 Early liquefaction due to B4C/SS eutectic reaction Melting point B 4 C ~2720K Stainless Steel ~1730K B 4 C/SS eutectic ~1500K Relocation of control blade[3] Melting temperatures of B4C & SS are 2720 K and 1730 K, respectively. Melting temperature of eutectic material is lower than the original materials. When the temperature exceed 1500K, the eutectic material starts to melt suddenly. Control rods melt firstly among other components. 19/05/2015 6
7 Objective In spite of its importance, few experimental research had been performed(ex: P. Hofmann (KIT) and H. Uetsuka (JAEA)). In the past, no visualization of the phenomena was reported. Difficult to know the dominant phenomenon during the liquefaction. Cannot characterize the phenomena in simulations. Visualizing reaction layer growth in order to create a database for simulation. Acquire the qualitative and quantitative information by image analysis. Provide boundary conditions( e.g. Temperature, Heat transfer ) 19/05/2015 7
8 Experimental
9 Specimen B4C powder is stuffed between SS plate. Filling rate was 47 %. We focused on the side SS plates during the experiments. Stainless Steel Plate B4C powder
10 42 mm 10 mm 15 mm Specimen(cont d) Specimen that has B4C powder between SS plates. Specimen was 4 mm in width & 35 mm in height. Measured the temperature with 4 thermocouples Front view Side view Tungsten heater Tungsten heater Specimen TCs TCs 2 mm 2 mm 4 mm 19/05/
11 Experimental setup Heat up the test piece with tungsten heater. Radiation heat transfer Sheathed thermocouples. Ar atmosphere inside the test facility. Power supply + Glass window Electrode Heater Heater Camera SS/B4C Electrode Ar Gas 19/05/
12 Visualization experiments
13 Conditions for each test case Average Temp. [ C] Case 1 L s s Case 1 R s s Case 2 R s Case 3 L s Case 3 R s σ shows the average temperature and standard deviation of each test case. Due to the different temperature of test piece in left and right side, which were analyzed separately and indicated by L and R. 19/05/
14 Temperature history B/L thermocouple was broken due to the reaction Temperature [ ] Top/Left Top/Right Bottom/Left Bottom/Right IR camera Time [s] 19/05/
15 Results of experiments On the left side, the eutectic reaction started and later it also started on the right side. Molten material invaded B4C region enhancing the diffusion. SS plates started to melt. Liquefied SS enhanced the diffusion of B4C. 19/05/
16 Results of experiments (cont d) The side SS plates were drastically molten. The middle part of the T.P. was molten due to not uniform heat flux profile in height direction. 2 cm Back plate does not melt because we coated it with cement. Result of the reaction 19/05/
17 The plots of results Correlation between the reaction layer thickness and the square root of time. Each plots obeyed a parabolic rate law. 19/05/
18 Arrhenius plots of experimental results The reaction rate constants for B 4 C powder/ss were obtained in the previous studies (Hering and Hofmann, 1994; Nagase et al., 1997). An obvious discontinuity in the temperature dependence of the parabolic rate law constant is seen between 1200 and 1225 C (Nagase et al., 1997). This discontinuity exists because the minimum melting temperature of Fe-B system is 1174 C and it starts to melt when it exceeds this temperature with certain amount of mixture. 19/05/
19 Conclusion The eutectic reaction between B4C powder & SS has been visualized. The temperature history during the experiment has been obtained. Qualitative knowledge about the growth of reaction zone has been obtained. The new correlation was proposed between 1181 and 1208 C 19/05/
20 Thank you for your attention! 19/05/
21 References [1] TOSHIBA Corporation, Advanced Boiling Water Reactor What s ABWR Control Rods and Control Rod Drive, m, (accessed ) [2] World Nuclear Association, Nuclear Fuel Fabrication, nuclear.org/info/nuclear-fuel-cycle/conversion-enrichment-and- Fabrication/Fuel-Fabrication/, (accessed ) [3] L. Sepold, S. Hagen, P. Hofmann and G. Schanz, Behavior of BWR-type Fuel Elements with B4C/Steel Absorber Tested under Severe Fuel Damage Conditions in the CORA Facility, Forschungszentrum Karlsruhe, FZKA-7447, 2009 [4] M. Kondo and Seiichi Koshizuka, Improvement of stability in moving particle semi-implicit method, International Journal for Numerical methods in Fluids, Vol. 65, p (2010) [5] Диаграммы состояния двойных металлических систем (4 тома), [6] Asril Pramutadi Andi Mustari and Y. Oka, Molten uranium eutectic interaction on iron-alloy by MPS method, Nuclear Engineering and Design, Vol. 278, p (2014) 19/05/
Symposium on Risk Integrated Engineering January 21, 2019, Takeda Hall, The Univ. Tokyo Researches on Severe Accident and Risk Engineering
Symposium on Risk Integrated Engineering January 21, 2019, Takeda Hall, The Univ. Tokyo Researches on Severe Accident and Risk Engineering Koji Okamoto The University of Tokyo okamoto@n.t.u-tokyo.ac.jp
More informationUnderstanding the effects of reflooding in a reactor core beyond LOCA conditions
Understanding the effects of reflooding in a reactor core beyond LOCA conditions F. Fichot 1, O. Coindreau 1, G. Repetto 1, M. Steinbrück 2, W. Hering 2, M. Buck 3, M. Bürger 3 1 - IRSN, Cadarache (FR)
More informationBehavior of high burnup fuel during LOCA - Key observations and test plan at JAEA -
Behavior of high burnup fuel during LOCA - Key observations and test plan at JAEA - Fumihisa Nagase Japan Atomic Energy Agency IAEA Technical Meeting on Fuel Behaviour and Modelling under Severe Transient
More informationZRO 2 AND UO 2 DISSOLUTION BY MOLTEN ZIRCALLOY
International Conference Nuclear Energy for New Europe 2002 Kranjska Gora, Slovenia, September 9-12, 2002 www.drustvo-js.si/gora2002 ZRO 2 AND UO 2 DISSOLUTION BY MOLTEN ZIRCALLOY J. Stuckert, A. Miassoedov,
More informationSIMULATION OF THE QUENCH-06 EXPERIMENT WITH MELCOR 1.8.5
International Conference Nuclear Energy in Central Europe 2001 Hoteli Bernardin, Portorož, Slovenia, September 10-13, 2001 www: http://www.drustvo-js.si/port2001/ e-mail: PORT2001@ijs.si tel.:+ 386 1 588
More informationQUENCH-14, QUENCH-16 and QUENCH-ALISA analysis
QUENCH-14, QUENCH-16 and QUENCH-ALISA analysis with RELAP5/SCDAPSIM MOD3.5(KIT) and MOD3.5+(KIT) Presenting authors: Olga Dutkiewicz, Krzysztof Marcinkiewicz Co-authors: Hiroshi Madokoro, dr Heinrich Muscher,
More informationFundamental Research Program for Removal of Fuel Debris
International Symposium on the Decommissioning of TEPCO s Fukushima Daiichi Nuclear Power Plant Unit 1-4 1 Fundamental Research Program for Removal of Fuel Debris March 14, 2012 Tadahiro Washiya Japan
More informationDRAFT: SEVERE FUEL DAMAGE EXPERIMENTS WITH ADVANCED CLADDING MATERIALS TO BE PERFORMED IN THE QUENCH FACILITY (QUENCH-ACM)
Proceedings of the 16th International Conference on Nuclear Engineering ICONE16 May 11-15, 2008, Orlando, Florida, USA ICONE16-48074 DRAFT: SEVERE FUEL DAMAGE EXPERIMENTS WITH ADVANCED CLADDING MATERIALS
More informationMinimizing Activation, Size and Costs and yet Maximizing Efficiency
Minimizing Activation, Size and Costs and yet Maximizing Efficiency An Engineering Challenge for Neutron Research Instruments Elbio Calzada MLZ is a cooperation between: Outline Introduction: Neutron Source
More informationCOOLING CHARACTERISTICS OF PWR-TYPE FUEL ELEMENT SIMULATORS TESTED IN THE QUENCH EXPERIMENTS
The 10 th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10) Seoul, Korea, October 5-9, 2003 COOLING CHARACTERISTICS OF PWR-TYPE FUEL ELEMENT SIMULATORS TESTED IN THE QUENCH
More informationEXPERIMENTS ON AIR INGRESS DURING SEVERE ACCIDENTS
13 th International Conference on Nuclear Engineering Beijing, China, May 16-20, 2005 ICONE13-50080 EXPERIMENTS ON AIR INGRESS DURING SEVERE ACCIDENTS Martin Steinbrück *, Alexei Miassoedov **, Gerhard
More informationSAFETY ENHANCEMENT TECHNOLOGY DEVELOPMENT WITH COLLABORATIVE INTERNATIONAL ACTIVITY
SAFETY ENHANCEMENT TECHNOLOGY DEVELOPMENT WITH COLLABORATIVE INTERNATIONAL ACTIVITY KENJI ARAI Toshiba Corporation Yokohama, Japan Email: kenji2.arai@toshiba.co.jp FUMIHIKO ISHIBASHI Toshiba Corporation
More informationPool Boiling Heat Transfer to Water/Lithium Bromide Mixture
International Conference on Challenges and Opportunities in Mechanical Engineering, Industrial Engineering and Management Studies 548 Pool Boiling Heat Transfer to Water/Lithium Bromide Mixture A. Sathyabhama
More informationCurrent Status of Interim Storage Facility for Spent Fuels in Japan
Current Status of Interim Storage Facility for Spent Fuels in Japan 19-21 May 2014, IAEA workshop for DPC Tatsuya Ishikawa Cask Procurement Group, Engineering Department Recyclable-Fuel Storage Company
More informationOVER VIEW OF ACCIDENT OF FUKUSHIMA DAI-ICHI NPSs AND FUTURE PLANNING TOWARD D&D
OVER VIEW OF ACCIDENT OF FUKUSHIMA DAI-ICHI NPSs AND FUTURE PLANNING TOWARD D&D 16 NOVEMBER, 2011 Hiroshi RINDO JAPAN ATOMIC ENERGY AGENCY Table of Contents 1. What s happened at Fukushima Dai-Ichi NPSs
More informationsevere accident progression in the BWR lower plenum and the modes of vessel failure
1 For Presentation at the ERMSAR Conference held in Marseilles, France, March 24-26, 2015 severe accident progression in the BWR lower plenum and the modes of vessel failure B. R. Sehgal S. Bechta Nuclear
More informationSIMULATION OF LIVE-L4 WITH ATHLET-CD
SIMULATION OF LIVE-L4 WITH ATHLET-CD T. Hollands, C. Bals Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) ggmbh Forschungszentrum, Boltzmannstraße 14, 85748 Garching, Germany thorsten.hollands@grs.de;
More informationCOMPARATIVE STUDIES ON THERMAL EFFICIENCY OF SINGLE AND DOUBLE GLAZED FLAT PLATE SOLAR WATER HEATER
COMPARATIVE STUDIES ON THERMAL EFFICIENCY OF SINGLE AND DOUBLE GLAZED FLAT PLATE SOLAR WATER HEATER J. Manikandan and B. Sivaraman Department of Mechanical Engineering, Annamalai University, Chidambaram,
More informationINVESTIGATION OF THE WETTING CHARACTERISTICS OF LIQUID Fe-19%Cr-10%Ni ALLOYS ON THE ALUMINA AND DOLOMITE SUBSTRATES AT 1873 K
INVESTIGATION OF THE WETTING CHARACTERISTICS OF LIQUID Fe-19%Cr-10%Ni ALLOYS ON THE ALUMINA AND DOLOMITE SUBSTRATES AT 1873 K Joonho Lee & Minsoo Shin Korea University, Korea Joo-Hyun Park University of
More informationOxygen Permeability through Internal Oxidation Zone in Fe Cr Alloys under Dry and Humid Conditions at 973 and K
, pp. 259 263 Oxygen Permeability through Internal Oxidation Zone in Fe Cr Alloys under Dry and Humid Conditions at 973 and 1 073 K Asep Ridwan SETIAWAN, 1) Mohd HANAFI BIN ANI, 2) Mitsutoshi UEDA, 2)
More informationThe PARAMETER test series
The PARAMETER test series V. Nalivaev 1, A. Kiselev 2, J.-S. Lamy 3, S. Marguet 3, V. Semishkin 4, J. Stuckert, Ch. Bals 6, K. Trambauer 6, T. Yudina 2, Yu. Zvonarev 7 1 Scientific Manufacturer Centre,
More informationTrial of capillary refining by porous CaO with molten slag
Trial of capillary refining by porous CaO with molten slag Toshihiro TANAKA, Masanori SUZUKI Division of Materials and Manufacturing Science, Graduate School of Engineering, Osaka University, 2-1 Suita,
More informationSafety design approach for JSFR toward the realization of GEN-IV SFR
Safety design approach for JSFR toward the realization of GEN-IV SFR Advanced Fast Reactor Cycle System R&D Center Japan Atomic Energy Agency (JAEA) Shigenobu KUBO Contents 1. Introduction 2. Safety design
More informationFigure 1(a) The maximum mass of ice melted (m) for difference mass of liquid X (M) are obtained and recorded in Table 1.
NAME : F.4 ( ) Marks: /70 FORM FOUR PHYSICS REVISION TEST on HEAT Time Allowed: 70 minutes This paper consists of two sections. Section A (50 marks) consists of the structure-type questions, and Section
More informationTHE NUCLEAR FUEL CYCLE
THE NUCLEAR FUEL CYCLE Uranium is a slightly radioactive metal that is found throughout the earth s crust It is about 500 times more abundant than gold and about as common as tin Natural uranium is a mixture
More informationIrradiation Assisted Stress Corrosion Cracking. By Topan Setiadipura [09M51695] (Obara Lab., Nuclear Engineering Dept., Tokyo Tech.
Introduction Short Review on Irradiation Assisted Stress Corrosion Cracking By Topan Setiadipura [09M51695] (Obara Lab., Nuclear Engineering Dept., Tokyo Tech.) Irradiation-assisted stress-corrosion cracking
More informationHydrogen isotopes permeation in a fluoride molten salt for nuclear fusion blanket
J. Plasma Fusion Res. SERIES, Vol. (5) Hydrogen isotopes permeation in a fluoride molten salt for nuclear fusion blanket Akira Nakamura, Satoshi Fukada and Ryosuke Nishiumi Department of Advanced Energy
More informationThe principle Of Tungsten Inert Gas (TIG) Welding Process
The principle Of Tungsten Inert Gas (TIG) Welding Process This chapter presents the principle of tungsten inert gas (TIG) welding process besides important components of TIG welding system and their role.
More informationTrial on the Applicaton of Capillary Phenomenon of Solid CaO to Desulfurization of Liquid Fe
Title Author(s) Citation Trial on the Applicaton of Capillary Phenomenon of Solid CaO to Desulfurization of Liquid Fe Tanaka, Toshihiro; Ogiso, Yumi; Ueda, Mitsuru; Lee, Joonho ISIJ INternational. 50(8)
More informationProfile LFR-47 RACHELE ITALY. Lead-Alloy Chemistry Laboratory. RACHELE (Reactions and Advanced CHEmistry for LEad) Lead/Lead-Bismuth Eutectic
Profile LFR-47 RACHELE ITALY GENERAL INFORMATION NAME OF THE ACRONYM COOLANT(S) OF THE LOCATION (address): OPERATOR CONTACT PERSON (name, address, institute, function, telephone, email): Lead-Alloy Chemistry
More informationCLAD STAINLESS STEELS AND HIGH-NI-ALLOYS FOR WELDED TUBE APPLICATION
CLAD STAINLESS STEELS AND HIGHNIALLOYS FOR WELDED TUBE APPLICATION Wolfgang Bretz Wickeder Westfalenstahl GmbH Hauptstrasse 6 D58739 Wickede, Germany Keywords: Cladding, Laser/TIG Welding, Combined SolderingWelding
More informationJ. Stuckert, M. Große, M. Steinbrück
Bundle reflood tests QUENCH-14 and QUENCH-15 with advanced cladding materials: comparable overview J. Stuckert, M. Große, M. Steinbrück Institute for Materials Research KIT University of of the State of
More informationVVER-440/213 - The reactor core
VVER-440/213 - The reactor core The fuel of the reactor is uranium dioxide (UO2), which is compacted to cylindrical pellets of about 9 height and 7.6 mm diameter. In the centreline of the pellets there
More informationThe international program Phebus FP (fission
1The safety of nuclear reactors 1 6 Results of initial Phebus FP tests FPT-0 and FPT-1 S. BOURDON (IRSN) D. JACQUEMAIN (IRSN) R. ZEYEN (JRC/PETTEN) The international program Phebus FP (fission products)
More informationMultiphase Flow Dynamics 4
Multiphase Flow Dynamics 4 Nuclear Thermal Hydraulics von Nikolay I Kolev 1. Auflage Multiphase Flow Dynamics 4 Kolev schnell und portofrei erhältlich bei beck-shop.de DIE FACHBUCHHANDLUNG Thematische
More informationIn-core measurements of fuel-clad interactions in the Halden reactor
In-core measurements of fuel-clad interactions in the Halden reactor Peter Bennett Halden Project IAEA Technical Meeting on Fuel Rod Instrumentation and In-Pile Measurement Techniques Halden, Norway 3
More informationGrade 11 Term 1. Welding Simulation Project
Grade 11 Term 1 Welding Simulation Project Unit/Topic: STSENGS873 Welding Simulation STS Performance Criteria: 1.1,1.4-1.6, 2.1-2.4 AQF Unit & PC: N/A to selected TAFE units (AWS positions,1g,2g,2f) Name:
More informationObservation and numerical simulation of melt pool dynamic and beam powder interaction during selective electron beam melting
Observation and numerical simulation of melt pool dynamic and beam powder interaction during selective electron beam melting T. Scharowsky, A. Bauereiß, R.F. Singer, C. Körner *Department of Materials
More informationExperiments of the LACOMECO Project at KIT
Experiments of the LACOMECO Project at KIT A. MIASSOEDOV 1, M. KUZNETSOV 1, M. STEINBRÜCK 1, S. KUDRIAKOV 2 Z. HÓZER 3, I. KLJENAK 4, R. MEIGNEN 5, J.M. SEILER 6, A. TEODORCZYK 7 1 KIT, Karlsruhe (DE)
More informationEXPERIMENTAL SIMULATION OF MOLTEN METAL FREEZING BEHAVIOR ONTO A STRUCTURE WITH A REACTOR SAFETY ANALYSIS CODE, SIMMER-III
NTHAS5: Fifth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety Jeju, Korea, November 26-29, 2006 NTHAS5-K005 EXPERMENTAL SMULATON OF MOLTEN METAL FREEZNG BEHAVOR ONTO A STRUCTURE WTH A REACTOR
More informationCountry feedback on General HTGR activities Contributions of Germany
meinschaft Mitglied der Helmholtz-Gem Country feedback on General HTGR activities Contributions of Germany Forschungszentrum Jülich, Germany Technical Meeting on Re-evaluation of Maximum Operating Temperatures
More informationTopics Fukushima 15 September 2015 No.70
Topics Fukushima 15 September 2015 No.70 Examination of reactor cores using laser Analysis of elemental composition in fuel debris became possible How is the present situation of the reactor cores inside
More informationEnsuring Spent Fuel Pool Safety
Ensuring Spent Fuel Pool Safety Michael Weber Deputy Executive Director for Operations U.S. Nuclear Regulatory Commission American Nuclear Society Meeting June 28, 2011 1 Insights from Fukushima Nuclear
More informationA Liquidation Strategy of Fukushima Daiichi Nuclear Power Plant: A new In-Situ Entombment Plan proposed
A Liquidation Strategy of Fukushima Daiichi Nuclear Power Plant: A new In-Situ Entombment Plan proposed May 27, 2011 Satoshi Sato satoshi@sato@iacdc.com International Access Corporation Abstract I studied
More informationLatest SCC Issues of Core Shroud and Recirculation Piping in Japanese BWRs
Transactions of the 7 th International Conference on Structural Mechanics in Reactor Technology (SMiRT 7) Prague, Czech Republic, August 7, 3 Paper # WG- Latest SCC Issues of Core Shroud and Recirculation
More informationChapter 7 Evaluation of Injection-Molding Phenomena Part 1: Measurement of temperature distribution in the molded materials
Chapter 7 Evaluation of Injection-Molding Phenomena Part 1: Measurement of temperature distribution in the molded materials 1. Evaluation of Injection-Molding Phenomena It is effective to evaluate the
More informationHigh-temperature oxidation and mutual interactions of materials during severe accidents in LWRs
High-temperature oxidation and mutual interactions of materials during severe accidents in LWRs Seminar at the Institute of Nuclear Chemistry and Technology, 2 March 214, Warsaw, Poland Institute for Applied
More informationSimultaneous Oxygen, Nitrogen and Hydrogen Determination of Metals. Dennis Lawrenz, John Hawkins
Simultaneous Oxygen, Nitrogen and Hydrogen Determination of Metals Dennis Lawrenz, John Hawkins LECO Corporation, St Joseph, Michigan, USA The inert gas fusion (IGF) principle has been used to determine
More informationX-ray fluorescence analysis of zinc and zinc iron alloy coated steel sheet
Technical articles X-ray fluorescence analysis of zinc and zinc iron alloy coated steel sheet Takao Moriyama* and Kenji Kodama* 1. Introduction Since it is possible to apply zinc to the surface of steel
More informationPreliminary Results of Three Dimensional Core Design in JAPAN
Preliminary Results of Three Dimensional Core Design in JAPAN Information Exchange Meeting on SCWR Development April 29, 2003 Toshiba Corporation The University of Tokyo Scope of SCWR Core Design (in Short
More informationMartin Steinbrück Karlsruhe Institute for Technology Postfach 1, D Karlsruhe, Germany
Study of Boron Behaviour in the Primary Circuit of Water Reactors under Severe Accident Conditions: a Comparison of Recent Integral and Separate-Effects Data Tim Haste, Frédéric Payot, Cristina Dominguez,
More informationTO STUDY THE EFFECT OF PROCESS PARAMETER ON GAS INTERRUPTION ON EN LOW ALLOY STEEL IN SMAW PROCESS
TO STUDY THE EFFECT OF PROCESS PARAMETER ON GAS INTERRUPTION ON EN-10213-2 LOW ALLOY STEEL IN SMAW PROCESS Sandeep Kumar Om Institute of Technology and Management,Hisar M Tech Scholars, Hisar, Haryana,
More informationA NEW APPARATUS FOR FLAME SPREAD EXPERIMENTS
th International Conference on Structural Mechanics in Reactor Technology (SMiRT ) - A NEW APPARATUS FOR FLAME SPREAD EXPERIMENTS Johan Mangs VTT Technical Research Centre of Finland, Espoo, Finland ABSTRACT
More informationTsunami Countermeasures at Hamaoka Nuclear Power Station -- Design and Construction of Tsunami Protection Wall
Tsunami Countermeasures at Hamaoka Nuclear Power Station -- Design and Construction of Tsunami Protection Wall 1. Overview of tsunami protection wall Chubu Electric Power Company s Hamaoka Nuclear Power
More informationTIG WELDING OPPORTUNITIES OF BIMETALLIC ENDLESS SAW BLADES
TIG WELDING OPPORTUNITIES OF BIMETALLIC ENDLESS SAW BLADES Ion MITELEA a, Dumitru-Daniel OCHIAN a, Mircea BURCA a, Ion-Dragos UTU a a POLITEHNICA UNIVERSITY OF TIMISOARA, Pta Victoriei,no. 1, Timisoara,Romania,
More informationLOCA analysis of high temperature reactor cooled and moderated by supercritical light water
GENES4/ANP23, Sep. 15-19, Kyoto, JAPAN Paper 116 LOCA analysis of high temperature reactor cooled and moderated by supercritical light water Yuki Ishiwatari 1*, Yoshiaki Oka 1 and Seiichi Koshizuka 1 1
More informationVISUALIZATION OF TRANSIENT INTERACTION PHENOMENA BETWEEN DROPLETS AND HOT WALLS AROUND LEIDENFROST TEMPERATURE FOR SUS304
Proceedings of the International Conference on Mechanical Engineering 2007 (ICME2007) 29-31 December 2007, Dhaka, Bangladesh ICME07- VISUALIZATION OF TRANSIENT INTERACTION PHENOMENA BETWEEN DROPLETS AND
More informationHastelloy C-2000 (UNS N06200)
Hastelloy C-2000 (UNS N06200) Hastelloy C-2000 is a versatile alloy that provides high resistance to variety of chemicals including sulfuric acid, hydrochloric acid and other strong acidic media. It offers
More informationSULFIDATION. From Rolled Alloys Report Number 94-72
SULFIDATION Environments containing sulfur may rapidly attack high nickel alloys. The problem is more severe under reducing, or low oxygen, environments. The higher the nickel the more sensitive the alloy
More informationHigh-Speed Infrared Imaging for Characterization of the Additive Manufacturing Process
14 th Quantitative InfraRed Thermography Conference High-Speed Infrared Imaging for Characterization of the Additive Manufacturing Process by M.A. Langevin*, A. Huot*, S. Boubanga*, P. Lagueux*, E. Guyot*
More informationHeat Transfer in Polymers
Heat Transfer in Polymers Martin Rides, Crispin Allen, Angela Dawson and Simon Roberts 19 October 2005 Heat Transfer in Polymers - Summary Introduction Thermal Conductivity Heat Transfer Coefficient Industrial
More informationF, 3 Toyokaiji Building, Nishi-Shimbashi, Minato-ku, Tokyo , Japan Published: March 2016
Ever since its establishment in August 2013, the International Research Institute for Nuclear Decommissioning (IRID) has been fully committed to an urgent challenge research and development of technologies
More informationPowder spreading in additive manufacturing. Sina Haeri James Weir Fluid Lab Mechanical and Aerospace Engineering University of Strathclyde
Powder spreading in additive manufacturing Sina Haeri James Weir Fluid Lab Mechanical and Aerospace Engineering University of Strathclyde Outline Overview of Additive Manufacturing Technologies Powder
More informationThe 4th Progress Report
The 4th Progress Report on the Investigation and Examination of Unconfirmed and Unresolved Issues on the Development Mechanism of the Fukushima Daiichi Nuclear Accident December 17, 2015 Tokyo Electric
More informationLecture - 06 Principle of Fusion Welding Processes: Gas Welding
Joining Technologies of Commercial Importance Dr. D. K. Dwivedi Department of Mechanical and Industrial Engineering Indian Institute of Technology Roorkee Lecture - 06 Principle of Fusion Welding Processes:
More informationExperimental Results of the QUENCH-16 Bundle Test on Air Ingress
Experimental Results of the QUENCH-16 Bundle Test on Air Ingress J. Stuckert, M. Steinbrück Karlsruhe Institute of Technology (KIT) Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen Tel: +49
More informationResearch and Development Programs for Decommissioning of Fukushima Daiichi Nuclear Power Station
WRFPM 2014 Sendai, Japan Research and Development Programs for Decommissioning of Fukushima Daiichi Nuclear Power Station September 15, 2014 KENDA Hirofumi International Research Institute for Nuclear
More informationTopics on Current Nuclear Regulation in Japan
Topics on Current Nuclear Regulation in Japan Commissioner Toyoshi Fuketa Nuclear Regulation Authority(NRA 26 th Annual Regulatory Information Conference Bethesda North Marriott Hotel & Conference Center
More informationQUENCHING PERFORMANCE IN NANOFLUIDS AND NANOPARTICLES-DEPOSITED SURFACES
QUENCHING PERFORMANCE IN NANOFLUIDS AND NANOPARTICLES-DEPOSITED SURFACES Kyung Mo Kim, In Cheol Bang School of Mechanical and Nuclear Engineering Ulsan National Institute of Science and Technology 50 UNIST-gil,
More informationFukushima Dai-ichi. Short overview of 11 March 2011 accidents and considerations. 3 rd EMUG Meeting ENEA Bologna April 2011
Fukushima Dai-ichi Short overview of 11 March 2011 accidents and considerations Marco Sangiorgi - ENEA 3 rd EMUG Meeting ENEA Bologna 11-12 April 2011 NPPs affected by Earthquake NPPs affected by Earthquake
More informationCore Design of a High Temperature Reactor Cooled and Moderated by Supercritical Light Water
GENES4/ANP2003, Sep. 15-19, 2003, Kyoto, JAPAN Paper 1041 Core Design of a High Temperature Reactor Cooled and Moderated by Supercritical Light Water Akifumi YAMAJI 1*, Yoshiaki OKA 2 and Seiichi KOSHIZUKA
More informationDry storage systems and aging management
Dry storage systems and aging management H.Issard, AREVA TN, France IAEA TM 47934 LESSONS LEARNED IN SPENT FUEL MANAGEMENT Vienna, 8-10 July 2014 AREVA TN Summary Dry storage systems and AREVA Experience
More informationPHEBUS REACTOR: THE DRIVING OF A SEVERE ACCIDENT
PHEBUS REACTOR: THE DRIVING OF A SEVERE ACCIDENT M.-C. ANSELMET, J. BONNIN, F. SERRE, G. AUGIER, S. BAYLE, J.-C. CABRILLAT, G. REPETTO Institut de Protection et de Sûreté Nucléaire, Département de Recherche
More informationThe new material irradiation infrastructure at the BR2 reactor. Copyright 2017 SCK CEN
The new material irradiation infrastructure at the BR2 reactor The new material irradiation infrastructure at the BR2 reactor Steven Van Dyck, Patrice Jacquet svdyck@sckcen.be Characteristics of the BR2
More informationLAS VEGAS, NV July 19-21, R. G. WYMER Vanderbilt University
OVERVIEW OF THE NUCLEAR FUEL CYCLE AND ITS CHEMISTRY SHORT COURSE : Introduction to Nuclear Chemistry and Fuel Cycle Separations LAS VEGAS, NV July 19-21, 2011 R. G. WYMER Vanderbilt University THE NUCLEAR
More informationPULP AND PAPER RESEARCH INSTITUTE OF CANADA INSTITUT CANADIEN DE RECHERCHES SUR LES PÂTES ET PAPIERS. Red Hot Video of Combusting Liquor & Smelt
Red Hot Video of Combusting Liquor & Smelt Laurie Frederick Doug Singbeil Joey Kish at Primary Airports Black Liquor Colloquium - Utah 13 May 2003 2 1 Observations Lifespan of a Combusting Particle Coating
More informationELECTRA-FCC: An R&D centre for Generation IV systems in Sweden. Janne Wallenius Professor Reactor Physics, KTH
ELECTRA-FCC: An R&D centre for Generation IV systems in Sweden Janne Wallenius Professor Reactor Physics, KTH What do Generation IV nuclear systems offer? Recycle of U-238 from spent fuel and enrichment
More informationThermal Surfacing Powder choice with ease
Thermal Surfacing Powder choice with ease Why Thermal Surfacing Thermal surfacing is a cost effective method to achieve high performance characteristics on exposed metallic surfaces. A metal object can
More information4.3 SAFETY RESEARCH PROGRAM OF LWR FUELS AND MATERIALS USING THE JAPAN MATERIALS TESTING REACTOR
4.3 SAFETY RESEARCH PROGRAM OF LWR FUELS AND MATERIALS USING THE JAPAN MATERIALS TESTING REACTOR Satoshi Hanawa a, Jin Ogiyanagi a, Yasuhiro Chimi a, Hideo Sasajima a, Jinichi Nakamura a, Yutaka Nishiyama
More informationCoimisiún na Scrúduithe Stáit State Examinations Commission
2014. M73 Coimisiún na Scrúduithe Stáit State Examinations Commission LEAVING CERTIFICATE EXAMINATION, 2014 ENGINEERING MATERIALS AND TECHNOLOGY (Higher level 300 marks) THURSDAY, 5 JUNE MORNING 9:30 12:30
More informationThermal Modeling and Experimental Validation in the LENS Process
The Eighteenth Solid Freeform Fabrication Symposium August 6-8, 6 2007, Austin, Texas Thermal Modeling and Experimental Validation in the LENS Process Liang Wang 1, Sergio D. Felicelli 2, James E. Craig
More informationExplosion Damage in the Unit 4 Reactor Building of Fukushima Daiichi Nuclear Power Plant
25 th ICDERS August 2 7, 2015 Leeds, UK Explosion Damage in the Unit 4 Reactor Building of Fukushima Daiichi Nuclear Power Plant Takashi Tsuruda Akita Prefectural University Yurihonjo, Akita, Japan 1 Introduction
More informationHigh Heat-transfer Titanium Sheet-HEET - for Heat Exchangers
High Heat-transfer Titanium Sheet-HEET - for Heat Exchangers Keitaro TAMURA *1, Yoshio ITSUMI *1, Dr. Akio OKAMOTO *1, Dr. Hideto OYAMA *2, Dr. Hirofumi ARIMA *3, Dr. Yasuyuki IKEGAMI *3 *1 Titanium Plant,
More informationWELDING TECHNOLOGY AND WELDING INSPECTION
WELDING TECHNOLOGY AND WELDING INSPECTION PRESENTED BY: GOPAL KUMAR CHOUDHARY SVL ENGINEERING SERVICES CHENNAI CONTENTS: DEFINATION TYPES OF WELDING ELECTRODE GEOMETRY EQUIPMENT QUALITY PROCESS SAFETY
More informationMYRRHA FUEL TRANSIENT TESTS PROJECT AT THE TRIGA-ACPR REACTOR
MYRRHA FUEL TRANSIENT TESTS PROJECT AT THE TRIGA-ACPR REACTOR CSABA ROTH, BRIAN BOER*, MIREA MLADIN, ADRIAN DATCU, GEORGIANA BUDRIMAN, CALIN TRUTA Institute for Nuclear Research Pitesti, Romania * SCK
More informationTemperature Effects on Draw Bead Friction for Advanced High-Strength Steels
Temperature Effects on Draw Bead Friction for Advanced High-Strength Steels Hua-Chu ( Michael ) Shih United States Steel Corporation Outline Background Draw bead/die cooling and temperature acquisition
More informationMODELING OF QUENCH-16 EXPERIMENT WITH MAAP4 SEVERE ACCIDENT CODE
MODELING OF QUENCH-16 EXPERIMENT WITH MAAP4 SEVERE ACCIDENT CODE E. BEUZET EDF R&D 1 Avenue du Général de Gaulle, 92140 Clamart, France emilie.beuzet@edf.fr M. STEINBRÜCK, J. STUCKERT Karlsruhe Institute
More informationNiobium Powder Production in Molten Salt by Electrochemical Pulverization
Niobium Powder Production in Molten Salt by Electrochemical Pulverization Boyan Yuan * and Toru H. Okabe ** *: Graduate Student, Department of Materials Engineering, University of Tokyo **: Associate Professor,
More informationDevelopment of Next-Generation Light Water Reactor in Japan
Development of Next-Generation Light Water Reactor in Japan IAEA-CN-164-3S07 T. Yamamoto a, K. Kurosaki a, Y. Ohga a, K. Tsuzuki a, T. Tanaka a, M. Matsuura b, A. Murase c, S. Shimizu d a The Institute
More informationHastelloy G-30 (UNS N06030) Chemical Composition
Hastelloy G-30 (UNS N06030) Hastelloy G-30 is commonly used for providing excellent resistance to chemical conditions. It offers resistance to nitric acid, phosphoric acid, hydrochloric acid and hydrofluoric
More information2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea
FRESH WATER QUENCHING OF ALLOYS OF NUCLEAR INTEREST INCLUDING FeCrAl FOR ACCIDENT TOLERANT FUEL CLADDING Michael Schuster 1, Cole Crawford 1, and Raul B. Rebak 1 1 GE Global Research: 1 Research Circle,
More informationAmorphous Brazing Foil
Amorphous Brazing Foil Delivering Advantages to Your Critical Applications www.metglas.com Copyright 2015, Metglas, Inc. All Rights Reserved Metglas, Inc. is a Fully Owned Subsidiary of Hitachi Metals
More informationHard-facing Material. Scope of Application. Characteristics. The Hard-facing Materials Cover:
Hard-facing Material The Hard-facing Materials Cover: Cast Tungsten Carbide (Ordinary and Spherical), Cemented Carbide Pellet (YQ), Spray Welding Powder (Ordinary and Spherical), Single-crystal WC Powder
More informationBriquette Smelting in Electric Arc Furnace to Recycle Wastes from Stainless Steel Production
Briquette Smelting in Electric Arc Furnace to Recycle Wastes from Stainless Steel Production Qi-xing YANG 1 2 2, Dong-feng HE 2 3 1 Abstract: Wastes from stainless steel production were briquetted together
More informationSCC of SG tubing and stainless steel (SS) pipes and welds (PWRs) - 1
International Conference on Water Chemistry of Nuclear Reactor Systems, 11-14 October 2004, San Francisco, EPRI in co-operation with the IAEA Participation: more than 200 experts from 23 countries; IAEA
More informationPost-Test Analysis of the QUENCH-13 Experiment
Post-Test Analysis of the QUENCH-13 Experiment Jon Birchley 1, Henrique Austregesilo 2, Christine Bals 2, Roland Dubourg 3, Tim Haste 1, Jean-Sylvestre Lamy 4, Terttaliisa Lind 1, Bernard Maliverney 4,
More informationINTRODUCTION IN FUKUSHIMA WATER LEAK PROBLEM
U.P.B. Sci. Bull., Series C, Vol. 78, Iss. 1, 2016 ISSN 2286-3540 INTRODUCTION IN FUKUSHIMA WATER LEAK PROBLEM Radu SECAREANU 1, Ilie PRISECARU 2 The purpose of the paper is to present the water leak problem
More informationApproval of Welding Consumables for High Strength Steels for Welded Structures
(1995) (Rev.1 1997 Rev.2 Apr 2018) Approval of Welding Consumables for High Strength Steels for Welded Structures 1. General 1.1 Scope 1.1.1 These requirements supplement the UR W17 and give the conditions
More informationCurrent Status of Research and Development on System Integration Technology for Connection between HTGR and Hydrogen Production System at JAEA
Current Status of Research and Development on System Integration Technology for Connection between HTGR and Hydrogen Production System at JAEA Hirofumi Ohashi, Yoshitomo Inaba, Tetsuo Nishihara, Tetsuaki
More informationProcess HEAT PROGRESS REPORT. Lauren Ayers Sarah Laderman Aditi Verma Anonymous student
Process HEAT PROGRESS REPORT Lauren Ayers Sarah Laderman Aditi Verma Anonymous student Outline System Diagram Heat Exchangers Compressors Heat Transport Heat Storage Required Inputs System Diagram Printed
More information