Country feedback on General HTGR activities Contributions of Germany
|
|
- Christal Flowers
- 5 years ago
- Views:
Transcription
1 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 g p g p and Accident Conditions for HTR Fuel and Structural Materials IAEA Headquarters,Vienna, June
2 Outline General Situation of Nuclear Energy in Germany HTR activities at the Research Center Jülich and at the Institute for Reactor Safety and Technology (RWTH Aachen University) Other HTR activities in Germany Outlook 2
3 Outline General Situation of Nuclear Energy in Germany HTR activities at the Research Center Jülich and at the Institute for Reactor Safety and Technology (RWTH Aachen University) Other HTR activities in Germany Outlook 3
4 Situation of Nuclear Energy in Germany (1) Consensus in 2000 between Government and utilities to phase out nuclear by 2021 Atomic Act of 2002 excludes construction of new NPP and reprocessing Decision in October 2010 for lifetime extension 8 years for 7 plants constructed before years for 10 younger plants 4
5 Situation of Nuclear Energy in Germany (2) Decision in June 2011 (after Fukushima) shutdown of 7 oldest plants plus Krümmel NPP other 9 plants have to phase out last German NPP will be shutdown in 2022 In general, the situation for nuclear activities in Germany is difficult, in particular for HTR related ones 5
6 Situation of Nuclear Energy in Germany (3) Following the actual German policy the remaining activities are focused on nuclear waste conservation of know-how and competence national R&D programs funded by the two federal ministries (Economics and Technology / Education and Research) Regarding HTR analytical activities (3D fluid mechanics, core behavior) experimental activities i i (fluid mechanics, dust behavior, graphite corrosion) 6
7 National Activities National projects or activities as parts of such ones GRS, IKE Stuttgart University (analytical: fluid mechanics, core behavior) LRST Aachen University and Technical University Dresden (experimental and analytical: investigations of dust behavior) Research Center Jülich (FZJ) (analytical: fluid mechanics for pebbles and block type in different scales, core behavior) 7
8 International Activities EC Framework Programme (FP)-7 (ARCHER, CARBOWASTE, GoFastR ) mainly analytical, different German partners OECD-LOFC Project (Loss of Forced Coolant, Japanese HTTR, GRS and FZJ) Co-operation between INET and FZJ Working group on rework of AVR operation (initiated by regional policy and FZJ board) 8
9 Outline General Situation of Nuclear Energy in Germany HTR activities at the Research Center Jülich and at the Institute for Reactor Safety and Technology (RWTH Aachen University) Other HTR activities in Germany Outlook 9
10 Scope of Activities at Research Center Jülich / RWTH-Aachen University Small scale experiments INDEX (high numbers) Integral experiments NACOK 2 (detailed investigation) Code validation CFX (fluid mechanics HTRs) Code validation HCP (fluid mechanics HTRs) 10
11 INDEX (small scale experiment) IR camera Laser INDEX : Induction Experiment Ø 95 TC Flow channel made of fused glass Induction coil (water cooled) camera Quadratic cross section (66 x 66 mm) Induction coil designed for 200 g graphite pyrometer 105 mm Inlet of cooling water glas pyrometer graphite sample induktive heatet up to 1200 C Max. temperature pebble 1200 C Outlet of cooling water Max. heating rate pebble 500 C/min h~300 First set up with single sphere (D=60 mm) Later pebble bed, block elements Thermocouple, pyrometer, IR camera Gas analytics (He, O 2, CO 2, CO) Particle Imaging Velocimetry (2D / 3D) a=67 flow chanel GAS (N2-21 C) 11
12 INDEX First Experiment with Single Pebble Inductive heated single sphere 700, 900, 1000, 1100, 1200 C Nitrogen flow 22 l/min 2D PIV of flow field above the pebble Measurements done in cold and hot state 12
13 CFX Calculation of Cool Down Experiment in INDEX Temperature [K] max x. pebble surface te emperature e / C Experiment Best Estimate Fine Grid time / s 13
14 INDEX: Modifications in Progress Optimizing setup for dust experiments New fused glass flow channel Ports for additional instrumentation New exhaust for particle loaded gas Moveable induction coil 14
15 NACOK2 Set-up of Block Experiment (1) 5 segments (upgradeable) Ceramic flow channel Base plate One ceramic block with holes Windows Simple chimney set up (strait, open gas inlet, open exhaust) 24 thermo couples Ultra sonic flow meter 2D Particle Imaging Velocimetry 15
16 NACOK2 Set-up of Block Experiment (2) 16
17 Temperatures during Block Experiment 1400 Temperatures TRC Zone 1 TRC Zone 2 TRC Zone TRC Zone 4 TRC Zone 5 Zone 1 solid 1000 Zone 1 Gas Zone 2 Window Zone 3 Wall 800 T [ C] Zone 4 Wall Zone 5 Wall Block center bottom 600 Block center middle Block center top Block edge top t [h] 17
18 NACOK2 Set-Up of Pebble Bed Simple chimney set up Heating rate 30 C/h 8 layers of ceramic pebbles (ordered) 200 spheres in total t (incl. half spheres at boundary) T max = 1000 C (upper pebble layer) Gas flow variation: 20, 30, 40 m³/h Four sets of PIV measurements 120 h experimental time 18
19 Temperatures during Pebble Bed Experiment 1200 Temperatures Zone 1 solid ld 1. Layer (1,1) 1. Layer (2,2) Layer (3,3) 1. Layer (4,4) Layer (5,5) 5. Layer (3,1) 5. Layer (3,3) 900 T [ C] 8. Layer (3, 3.5) Zone 2 wall 800 Zone 3 wall Zone 4 wall Zone 5 wall t [h]
20 PIV Measurement at 1000 C, flow rate 20 m³/h gas flow 20m³/h 20
21 Development of HTR Code Package (HCP) Objective: "Design, implementation and validation of software for the simulation of V/HTRs applying the latest programming techniques and standards." 21
22 Development of the dust module STAR (1) Staub- (dust) Transportt convective dust exchange between meshes interaction of dust concentration with deposition and resuspension Ablagerung (deposition) implementation of theoretical / semi-empirical correlations modeling of dust behavior on the surface for adhesive forces Resuspensionp implementation of the quasi-static Rock n Roll model 22
23 Development of the dust module STAR (2) Developed for the simulation of dust behavior in HTR Estimation of the source term due to dust for depressurization of the HTR-Module Rough assessment of activity released with the INES scale: Level 3 event for design basis accident (DBA) Level 4 event (unfavorable assumptions) for beyond DBA 23
24 Development of the dust module STAR (3) Future work improved simulation of dust in confinement (within ARCHER) further validation / improvement of STAR with focus on conditions representative for HTR (project TARGET) 24
25 Outline General Situation of Nuclear Energy in Germany HTR activities at the Research Center Jülich and at the Institute for Reactor Safety and Technology (RWTH Aachen University) Other HTR activities in Germany Outlook 25
26 Other HTR Related Activities in Germany Excerpt of activities: TU Dresden Development of SiC-Coatings by pulsed laser deposition Development of so-called Pebble-Mill to generate dust Dust deposition experiments Helmholtz-Zentrum Dresden-Rossendorf Development of reactor dynamics code DYN3D 26
27 Activities of IKE Stuttgart on HTR Development of a transient 3-d fluid mechanics code ATTICA3D with porous medium approach Coupling via interface with transient 3-d neutronic transport code TORT-TD Both pebble-type and block-type fuel elements AVR Reactor Pebble fuel elements Block fuel elements 27
28 IKE - Validation of ATTICA3D with the HTR-10 CRP-5 Benchmark: Temperature distribution at full power Control rod withdrawal at part load (3MW) Loss of flow at part load (3MW) Parameter Full power Part load Thermal power 10 MW 3 MW Inlet temperature 250 C 250 C Mean outlet temperature ~700 C ~650 C Helium mass flow 4.32 kg/s System pressure 30 bar 25 bar 28
29 Activities of Institute for Transuranium Elements (ITU) KüFA Test on HFR-EU1bis/5 Fuel element irradiated in HFR Petten Consistent ratio of 137 Cs and 134 Cs low level from other contamination sources No 85 Kr release could be detected (possible volatilization of the trapped fission gas) HFR-EU1bis/5 pebble features highest release from that irradiation campaign KüFA Test on AE to determine accuracy limits of KüFA setup Element irradiated in AVR, 3.56 % fima Very low release levels due to low burnup Accuracy limits of KüFA setup have been determined 29
30 Activities of Institute for Transuranium Elements (ITU) Spatial distribution of Caesium on condensation plates investigated with a tailored collimator Caesium is deposited on the entire surface with a ring profile of higher concentration around the centre 137 Cs distribution Stainless steel condensation plate Cs-137 conc. on a plate at accident temperature 1600 CfromtheHFREU1bis/5 HFR-EU1bis/5 test 30
31 Outline General Situation of Nuclear Energy in Germany HTR activities at the Research Center Jülich and at the Institute for Reactor Safety and Technology (RWTH Aachen University) Other HTR activities in Germany Outlook 31
32 Outlook German activities funded until 2015 Main objectives to be achieved until then first version of HTR Code Package (HCP) extension of the experimental data base for fluid mechanics and graphite dust behaviour, e.g. for MGT-3D capability of performing predictive calculations for block-type fuel HTR 32
Very High Temperature Reactor
Very High Temperature Reactor LI Fu GIF VHTR SSC Chair INET, Tsinghua University, China GIF Symposium San Diego November 15-16, 2012 Outline 1. Original VHTR Features 2. Key VHTR Development Targets 3.
More informationnuclear science and technology
EUROPEAN COMMISSION nuclear science and technology Co-ordination and Synthesis of the European Project of Development of HTR Technology (HTR-C) Contract No: FIKI-CT-2000-20269 (Duration: November 2000
More informationThe Next Generation Nuclear Plant (NGNP)
The Next Generation Nuclear Plant (NGNP) Dr. David Petti Laboratory Fellow Director VHTR Technology Development Office High Temperature, Gas-Cooled Reactor Experience HTGR PROTOTYPE PLANTS DEMONSTRATION
More informationModeling of Fuel Performance and Fission Product Release Behavior
Mitglied der Helmholtz-Gemeinschaft Modeling of Fuel Performance and Fission Product Release Behavior IEK-6, Research Center Jülich, Germany IAEA Training Course on HTGR Technologies, Beijing, China, October
More informationThermal Fluid Characteristics for Pebble Bed HTGRs.
Thermal Fluid Characteristics for Pebble Bed HTGRs. Frederik Reitsma IAEA Course on High temperature Gas Cooled Reactor Technology Beijing, China Oct 22-26, 2012 Overview Background Key T/F parameters
More informationThermal Response of a High Temperature Reactor during Passive Cooldown under Pressurized and Depressurized Conditions
2nd International Topical Meeting on HIGH TEMPERATURE REACTOR TECHNOLOGY Beijing, CHINA, September 22-24, 2004 #Paper F02 Thermal Response of a High Temperature Reactor during Passive Cooldown under Pressurized
More informationConcept and technology status of HTR for industrial nuclear cogeneration
Concept and technology status of HTR for industrial nuclear cogeneration D. Hittner AREVA NP Process heat needs from industry Steam networks In situ heating HTR, GFR 800 C VHTR > 800 C MSR 600 C SFR, LFR,
More informationJoint ICTP-IAEA Advanced School on the Role of Nuclear Technology in Hydrogen-Based Energy Systems June 2011
2245-10 Joint ICTP-IAEA Advanced School on the Role of Nuclear Technology in Hydrogen-Based Energy Systems 13-18 June 2011 The Part 3: Nuclear Process Heat Reactors Research Center Juelich Institute for
More informationOECD Transient Benchmarks: Preliminary Tinte Results TINTE Preliminary Results
OECD Transient Benchmarks: Preliminary Tinte Results Presentation Overview The use of Tinte at PBMR Tinte code capabilities and overview Preliminary Tinte benchmark results (cases1-6) The use of Tinte
More informationSafety Issues for High Temperature Gas Reactors. Andrew C. Kadak Professor of the Practice
Safety Issues for High Temperature Gas Reactors Andrew C. Kadak Professor of the Practice Major Questions That Need Good Technical Answers Fuel Performance Normal operational performance Transient performance
More informationApplication of CFD for nuclear reactor safety analyses
Application of CFD for nuclear reactor safety analyses Bogdán Yamaji assistant researcher Institute of Nuclear Techniques Budapest University of Technology and Economics 11-12 June 2009 2nd Consultancy
More informationJoint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies May 2008
1944-19 Joint ICTP-IAEA Workshop on Nuclear Reaction Data for Advanced Reactor Technologies 19-30 May 2008 Gas-Cooled Reactors Technology Options, Operating Research Reactors and Demonstration Plant Project
More information20 Years of German R&D on Nuclear Heat Applications
Mitglied der Helmholtz-Gemeinschaft 20 Years of German R&D on Nuclear Heat Applications Werner von Lensa, Karl Verfondern Research Centre Jülich, Germany 4th Int. Freiberg Conference on IGCC & XtL Technologies
More informationNaturally Safe HTGR in the response to the Fukushima Daiichi NPP accident
IAEA Technical Meeting on on Re evaluation of Maximum Operating Temperatures and Accident Conditions for High Temperature Reactor Fuel and Structural Materials, 10 12 July 2012, Vienna, Austria Naturally
More informationTHE PATH TOWARDS A GERMANE SAFETY AND LICENSING APPROACH FOR MODULAR HIGH TEMPERATURE GAS-COOLED REACTORS ABSTRACT
THE PATH TOWARDS A GERMANE SAFETY AND LICENSING APPROACH FOR MODULAR HIGH TEMPERATURE GAS-COOLED REACTORS FREDERIK REITSMA International Atomic Energy Agency (IAEA) Vienna International Centre, PO Box
More informationVHTR System Prof. Dr. LI Fu
VHTR System Prof. Dr. LI Fu GIF VHTR SSC INET, Tsinghua University, China GIF Symposium, Chiba, Japan May 19, 2015 Outlines What s VHTR? How about VHTR? What are main R&D topics? How to collaborate in
More informationGerman Experimental Activities for Advanced Modelling and Validation Relating to Containment Thermal Hydraulics and Source Term
German Experimental Activities for Advanced Modelling and Validation Relating to Containment Thermal Hydraulics and Source Term H.-J. Allelein 1,2, S. Gupta 3, G. Poss 3, E.-A. Reinecke 2, F. Funke 4 1
More informationDESIGN OF CATALYTIC RECOMBINERS FOR SAFE REMOVAL OF HYDROGEN FROM FLAMMABLE GAS MIXTURES
DESIGN OF CATALYTIC RECOMBINERS FOR SAFE REMOVAL OF HYDROGEN FROM FLAMMABLE GAS MIXTURES Reinecke, E.-A. 1, Kelm, S. 1, Struth, S. 1, Granzow, Ch. 1, and Schwarz, U. 2 1 Institute for Energy Research -
More informationThe Nuclear Simulation Chain of GRS
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) ggmbh The Nuclear Simulation Chain of GRS Andreas Schaffrath (andreas.schaffrath@grs.de) Sebastian Buchholz (sebastian.buchholz@grs.de) Anne Krüssenberg
More informationThe Nuclear Simulation Chain of GRS
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) ggmbh The Nuclear Simulation Chain of GRS Andreas Schaffrath (andreas.schaffrath@grs.de) Sebastian Buchholz (sebastian.buchholz@grs.de) Anne Krüssenberg
More informationCOMPARISON OF FUEL LOADING PATTERN IN HTR-PM
2nd International Topical Meeting on HIGH TEMPERATURE REACTOR TECHNOLOGY Beijing, CHINA, September 22-24, 2004 #Paper C23 COMPARISON OF FUEL LOADING PATTERN IN HTR-PM Fu Li, Xingqing Jing Institute of
More informationPRESENT STATUS OF THE HIGH TEMPERATURE ENGINEERING TEST REACTOR (HTTR)
PRESENT STATUS OF THE HIGH TEMPERATURE ENGINEERING TEST REACTOR (HTTR) Shusaku Shiozawa * Department of HTTR Project Japan Atomic Energy Research Institute (JAERI) Japan Abstract It is essentially important
More informationModule 09 High Temperature Gas Cooled Reactors (HTR)
c Module 09 High Temperature Gas Cooled Reactors (HTR) Prof.Dr. H. Böck Vienna University of Technology /Austria Atominstitute Stadionallee 2, 1020 Vienna, Austria boeck@ati.ac.at Development of Helium
More informationSafety Requirements for HTR Process Heat Applications
HTR 2014 Conference, Oct. 2014, Weihai, China Norbert Kohtz (TÜV Rheinland), Michael A. Fütterer (Joint Research Centre): Safety Requirements for HTR Process Heat Applications Outline 1. Introduction 2.
More informationThe European nuclear industry and research approach for innovation in nuclear energy. Dominique Hittner Framatome-ANP EPS, Paris, 3/10/2003
The European nuclear industry and research approach for innovation in nuclear energy Dominique Hittner Framatome-ANP EPS, Paris, 3/10/2003 Contents The EPS and MIT approach The approach of the European
More informationClosing Remarks and Action Plan PBMR COUPLED NEUTRONICS/THERMAL HYDRAULICS TRANSIENT BENCHMARK THE PBMR-400 CORE DESIGN
Closing Remarks and Action Plan PBMR COUPLED NEUTRONICS/THERMAL HYDRAULICS TRANSIENT BENCHMARK THE PBMR-400 CORE DESIGN OECD Interlaken, PBMR400 Switzerland T5.0 September 14 September 14, 2008 2008 1
More informationHTR-PM Project Status and Test Program
IAEA TWG-GCR-22 HTR-PM Project Status and Test Program SUN Yuliang Deputy Director, INET/ Tsinghua University March 28 April 1, 2011 1 Project organization Government INET R&D, general design, design of
More informationThe design features of the HTR-10
Nuclear Engineering and Design 218 (2002) 25 32 www.elsevier.com/locate/nucengdes The design features of the HTR-10 Zongxin Wu *, Dengcai Lin, Daxin Zhong Institute of Nuclear Energy and Technology, Tsinghua
More informationHTGR Safety Design Fundamental Safety Functions Safety Analysis Decay heat removal Criticality
HTGR Safety Design Fundamental Safety Functions Safety Analysis Decay heat removal Criticality Frederik Reitsma IAEA Course on High temperature Gas Cooled Reactor Technology Oct 22-26, 2012 Content / Overview
More informationConcept Design and Thermal-hydraulic Analysis for Helium-cooled ADS
Concept Design and Thermal-hydraulic Analysis for Helium-cooled ADS Tianji Peng 1, Zhiwei Zhou 1, Xuanyu Sheng 1 and Long Gu 2 1: Institute of Nuclear and New Energy Technology (INET), Collaborative Innovation
More informationChapter 4 THE HIGH TEMPERATURE GAS COOLED REACTOR TEST MODULE CORE PHYSICS BENCHMARKS
Chapter 4 THE HIGH TEMPERATURE GAS COOLED REACTOR TEST MODULE CORE PHYSICS BENCHMARKS 4.1 HTR-10 GENERAL INFORMATION China has a substantial programme for the development of advanced reactors that have
More informationHTTR test program towards coupling with the IS process
HTTR test program towards coupling with the IS process T. Iyoku, N.Sakaba, S. Nakagawa, Y.Tachibana, S. Kasahara, and K.Kawasaki Japan Atomic Energy Agency (JAEA) 1 Contents 1. Outline of the HTTR (High
More informationHTR System Integration in Europe and South Africa
HTR System Integration in Europe and South Africa M. Fütterer (JRC, Netherlands) F. Roelofs (NRG, Netherlands) J. Ruer (SAIPEM, France) P. Cuadrado Garcia (EA, Spain) J. Cetnar (AGH, Poland) D. Knoche
More informationREACTOR TECHNOLOGY DEVELOPMENT UNDER THE HTTR PROJECT
REACTOR TECHNOLOGY DEVELOPMENT UNDER THE HTTR PROJECT Takakazu TAKIZUKA Japan Atomic Energy Research Institute The 1st COE-INES International Symposium, INES-1 October 31 November 4, 2004 Keio Plaza Hotel,
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 informationANTARES The AREVA HTR-VHTR Design PL A N TS
PL A N TS ANTARES The AREVA HTR-VHTR Design The world leader in nuclear power plant design and construction powers the development of a new generation of nuclear plant German Test facility for HTR Materials
More informationExperimental and Analytical Results on H 2 SO 4 and SO 3 Decomposer for IS Process Pilot Plant
Experimental and Analytical Results on H 2 SO 4 and SO 3 Decomposer for IS Process Pilot Plant A. Terada, Y. Imai, H. Noguchi, H. Ota, A. Kanagawa, S. Ishikura, S. Kubo, J. Iwatsuki, K. Onuki and R. Hino
More informationModule 11 High Temperature Gas Cooled Reactors (HTR)
Prof.Dr. H. Böck Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria boeck@ati.ac.at Module 11 High Temperature Gas Cooled Reactors (HTR) 1.10.2013 Development of Helium Reactor
More informationFLOW & HEAT TRANSFER IN A PACKED BED - TRANSIENT
FLOW & HEAT TRANSFER IN A PACKED BED - TRANSIENT This case study demonstrates the transient simulation of the heat transfer through a packed bed with no forced convection. This case study is applicable
More informationInstitute of Nuclear Technology and Energy Systems
Institute of Nuclear Technology and Energy Systems Experimental and Analytical Investigation of the Performance of Heat Pipes for Residual Heat Removal from Spent Fuel Pools J. Starflinger, C. Graß, R.
More informationHTR related activities in The Netherlands
HTR related activities in The Netherlands Aliki van Heek 28 March 2011 Organisations in The Netherlands HTR related research is carried out by: - NRG - Delft University of Technology 2 Dutch nuclear research
More informationNGNP Licensing Approach & Status
www.inl.gov NGNP Licensing Approach & Status IAEA Course on High Temperature Gas Cooled Reactor Technology Tsinghua University, Beijing October 22-26, 2012 Presented by: Javier Ortensi Based on material
More informationModule 11 High Temperature Gas Cooled Reactors (HTR)
Prof.Dr. Böck Technical University Vienna Atominstitut Stadionallee 2, 1020 Vienna, Austria ph: ++43-1-58801 141368 boeck@ati.ac.at Module 11 High Temperature Gas Cooled Reactors (HTR) 1.3.2017 Development
More informationThe HTR/VHTR Project in Framatome ANP
The HTR/VHTR Project in Framatome ANP Framatome ANP Dominique HITTNER HTR-VHTR Project R&D manager Framatome ANP Framatome ANP The reference concept of ANTARES programme: a flexible heat source for heat
More informationDESIGN, SAFETY FEATURES & PROGRESS OF HTR-PM. Yujie DONG INET, Tsinghua University, China January 24, 2018
DESIGN, SAFETY FEATURES & PROGRESS OF HTR-PM Yujie DONG INET, Tsinghua University, China January 24, 2018 Meet the Presenter Dr. Dong is a Professor in Nuclear Engineering at the Tsinghua University, Beijing,
More informationOECD / NEA workshop NI 2050 Paris, 7 th and 8 th July 2015
OECD / NEA workshop NI 2050 Paris, 7 th and 8 th July 2015 Overview on the German situation with a focus on the HGF programme: Nuclear Waste Management, Safety and Radiation Research () Programme speaker
More informationPresent Status and Future Plan of HTTR Project
Present Status and Future Plan of HTTR Project Tatsuo Iyoku *, Toshio Nakazawa, Kozou Kawasaki, Hideyuki Hayashi, and Seigo Fujikawa Department of HTTR Project, Japan Atomic Energy Research Institute Narita-cho,
More informationELFR The European Lead Fast Reactor DESIGN, SAFETY APPROACH AND SAFETY CHARACTERISTICS. Alessandro Alemberti
ELFR The European Lead Fast Reactor DESIGN, SAFETY APPROACH AND SAFETY CHARACTERISTICS Alessandro Alemberti Alessandro.Alemberti@ann.ansaldo.it TECHNICAL MEETING ON IMPACT OF FUKUSHIMA EVENT ON CURRENT
More informationThe High Temperature Gas-cooled Reactor
The High Temperature Gas-cooled Reactor Safety considerations of the (V)HTR-Modul Kugeler, K., Nabielek, H., Buckthorpe, D. Editors: Scheuermann, W., Haneklaus, N., Fütterer, M. 2017 EUR 28712 EN This
More informationSteady State Temperature Distribution Investigation of HTR Core
Journal of Physics: Conference Series PAPER OPEN ACCESS Steady State Temperature Distribution Investigation of HTR Core To cite this article: Sudarmono et al 2018 J. Phys.: Conf. Ser. 962 012040 View the
More informationQUALIFICATION OF THE SYSTEM CODE AC² (SUBMODULE ATHLET) FOR THE SAFETY ASSESSMENT OF PASSIVE RESIDUAL HEAT REMOVAL SYSTEMS
QUALIFICATION OF THE SYSTEM CODE AC² (SUBMODULE ATHLET) FOR THE SAFETY ASSESSMENT OF PASSIVE RESIDUAL HEAT REMOVAL SYSTEMS D. VON DER CRON, S. BUCHHOLZ, A. SCHAFFRATH Gesellschaft für Anlagen- und Reaktorsicherheit
More informationSafety Design of HTGR by JAEA in the light of the Fukushima Daiichi accident
Technical Meeting on the Safety of High Temperature Gas Cooled Reactors in the Light of the Fukushima Daiichi Accident, 8-11 April 2014, IAEA Head quarters, Vienna, Austria Safety Design of HTGR by JAEA
More informationVery-High-Temperature Reactor System
Atomic Energy Society of Japan Journal of NUCLEAR SCIENCE and TECHNOLOGY (JNST) Very-High-Temperature Reactor System Ing. S. BOUČEK 1, Ing. R. VESECKÝ 2 1 Faculty of Electrical Engineering, Czech Technical
More informationAn Overview of the DOE Advanced Gas Reactor Fuel Development and Qualification Program
An Overview of the DOE Advanced Gas Reactor Fuel Development and Qualification Program David Petti Technical Director AGR Program ARWIF Oak Ridge, TN Feb. 16, 2005 Coated Particle Fuel Performance Is at
More informationOperation of the High-Temperature Engineering Test Reactor
Operation of the High-Temperature Engineering Test Reactor Nozomu Fujimoto, Naoki Nojiri, Yukio Tachibana and Toshihiko Mizushima Department of HTTR Japan Atomic Energy Agency (JAEA) -1- Contents 1. 1.
More informationX-energy Introduction
X-energy Introduction NUPIC Vendor Meeting Dr. Martin van Staden VP Xe-100 Program Manager June 22, 2016 2016 X Energy, LLC, all rights reserved @xenergynuclear Reimagining Nuclear Energy X-energy is reimagining
More informationOregon State University s Small Modular Nuclear Reactor Experimental Program
Oregon State University s Small Modular Nuclear Reactor Experimental Program IEEE Conference on Technologies for Sustainability August 1, 2013 Portland, Oregon Brian Woods Oregon State University brian.woods@oregonstate.edu,
More informationGerman SFR Research and European Sodium Fast Reactor Project
German SFR Research and European Sodium Fast Reactor Project B. Merk Institute of Resource Ecology (FWO) Helmholtz-Zentrum Dresden-Rossendorf with special thanks to E. Fridman, G. Gerbeth (FWD), A. Vasile
More informationR&D activities related to nuclear fuel performance and technology at the DG JRC. Paul VAN UFFELEN
R&D activities related to nuclear fuel performance and technology at the DG JRC Paul VAN UFFELEN 1 Introduction 2 JRC Core Staff (2004) Institute for Reference Materials and Measurements Institute for
More informationAdvanced Reactors Mission, History and Perspectives
wwwinlgov Advanced Reactors Mission, History and Perspectives Phillip Finck, PhD Idaho National Laboratory Senior Scientific Advisor June 17, 2016 A Brief History 1942 CP1 First Controlled Chain Reaction
More informationThe Gen IV Modular Helium Reactor
The Gen IV Modular Helium Reactor and its Potential for Small and Medium Grids presented to Society of Nuclear Engineers of Croatia 26 January 2007 by David E. Baldwin, Ph.D. Sustainable Energy has Become
More informationDevelopment of a DesignStage PRA for the Xe-100
Development of a DesignStage PRA for the Xe-100 PSA 2017 Pittsburgh, PA, September 24 28, 2017 Alex Huning* Karl Fleming Session: Non-LWR Safety September 27th, 1:30 3:10pm 2017 X Energy, LLC, all rights
More informationModular Helium Reactor (MHR) for Oil Sands Extraction
Modular Helium Reactor (MHR) for Oil Sands Extraction Alexander Telengator and Arkal Shenoy General Atomics 30th Annual CNS Conference 1 WORLD ENERGY COMPOSITION Fossil fuels provide ~ 85% of World energy
More informationFast Reactor Research in Dresden-Rossendorf
Fast Reactor Research in Dresden-Rossendorf B. Merk Department of Reactor Safety at Institute of Resource Ecology Helmholtz-Zentrum Dresden-Rossendorf TWG-FR, Chicago 2012 Text optional: Institutsname
More informationThorium Fuel Cycle Activities in IAEA
Thorium Fuel Cycle Activities in IAEA Uddharan Basak Nuclear Fuel Cycle and Material Section Division of Nuclear Fuel Cycle and Waste Technology Department of Nuclear Energy IAEA 1 International Atomic
More informationJülich, Author: Peter Pohl
Author: Peter Pohl Jülich, 18.08.2005 Pl/pi. OUR HTGR MANIFESTO Motivation In a world of new nuclear concepts, a profusion of ideas, and many newcomers to the HTGR, the author, having been chiefly involved
More informationInternational status of HTGRs
International status of HTGRs by Juergen Kupitz and John B. Dee Advanced nuclear power systems For more than 25 years, development programmes on the high-temperature gas-cooled reactor (HTGR) have been
More informationHTR Research and Development Program in China
HTR Research and Development Program in China Yuanhui XU Institute of Nuclear and New Energy Technology Tsinghua University, Beijing, China 2004 Pacific Basin Nuclear Conference And Technology Exhibit
More informationUnique Irradiation Rigs developed for the HFR Petten at the JRC-IE;
Unique Irradiation Rigs developed for the HFR Petten at the JRC-IE; details of LYRA, QUATTRO and Fuel Irradiation facilities JRC-IE, Institute For Energy, Petten L.Debarberis, B. Acosta, J.Degmova, A.Zeman,
More informationCO2-free Hydrogen production: the Nuclear route
CO2-free Hydrogen production: the Nuclear route Jan Leen Kloosterman Adrian Verkooijen Hydrogen-Carbon ratio in energy mix Shares in primary energy Hydrogen-Carbon ratio in energy mix Shares in primary
More informationDELIVERABLE (D-N : 2.2) Status of Rim and Grain Boundary Diffusion Experiments (12 months)
F DELIVERABLE (D-N : 2.2) Status of Rim and Grain Boundary Diffusion Experiments (12 months) (Contract Number: FP7-295722) D.H. Wegen, P. Carbol, H. Curtius, J. Vandenborre 2 0 12 2/11 Classification:
More informationPBMR design for the future
Nuclear Engineering and Design 222 (2003) 231 245 PBMR design for the future A. Koster, H.D. Matzner, D.R. Nicholsi PBMR Pty (Ltd), P.O. Box 9396, Centurion 0046, South Africa Received 2 May 2002; received
More informationFast and High Temperature Reactors for Improved Thermal Efficiency and Radioactive Waste Management
What s New in Power Reactor Technologies, Cogeneration and the Fuel Cycle Back End? A Side Event in the 58th General Conference, 24 Sept 2014 Fast and High Temperature Reactors for Improved Thermal Efficiency
More informationANTARES Application for Cogeneration. Oil Recovery from Bitumen and Upgrading
ANTARES Application for Cogeneration Oil Recovery from Bitumen and Upgrading Michel Lecomte Houria Younsi (ENSEM) Jérome Gosset (ENSMP) ENC Conference Versailles 11-14 December 2005 1 Presentation Outline
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 informationDESIGN AND SAFETY- SUPPORT ANALYSES OF AN IN-PILE MOLTEN SALT LOOP IN THE HFR
DESIGN AND SAFETY- SUPPORT ANALYSES OF AN IN-PILE MOLTEN SALT LOOP IN THE HFR stempniewicz@nrg.eu M.M. Stempniewicz, E.A.R. de Geus, F. Alcaro, P.R. Hania, K. Nagy, N.L. Asquith, J. de Jong, L. Pool, S.
More information4.2 DEVELOPMENT OF FUEL TEST LOOP IN HANARO
4.2 DEVELOPMENT OF FUEL TEST LOOP IN HANARO Sungho Ahn a, Jongmin Lee a, Suki Park a, Daeyoung Chi a, Bongsik Sim a, Chungyoung Lee a, Youngki Kim a and Kyehong Lee b a Research Reactor Engineering Division,
More informationBenchmark Specification for HTGR Fuel Element Depletion. Mark D. DeHart Nuclear Science and Technology Division Oak Ridge National Laboratory
I. Introduction Benchmark Specification for HTGR Fuel Element Depletion Mark D. DeHart Nuclear Science and Technology Division Oak Ridge National Laboratory Anthony P. Ulses Office of Research U.S. Nuclear
More informationDesign of Solid Breeder Test Blanket Modules in JAERI
Design of Solid Breeder Test Blanket Modules in JAERI Presented by: S. Suzuki, Blanket Engineering Lab., Japan Atomic Energy Research Institute, JAERI Contents 1. Outline of blanket development in JAERI
More informationMSc Mini-Dissertation. Modelling of fission product release from TRISO fuel during accident conditions: Benchmark code comparison
MSc Mini-Dissertation Modelling of fission product release from TRISO fuel during accident conditions: Benchmark code comparison Student: Supervisor: Co-Supervisor: Alastair Ramlakan Prof. Eben Mulder
More informationGases, in Particular Helium, as Nuclear Reactor Coolant
Gases, in Particular Helium, as Nuclear Reactor Coolant E. Bubelis KIT University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association www.kit.edu Contents Gas-cooled
More informationWir schaffen Wissen heute für morgen. Nuclear energy and research in Switzerland, its outlook and activities on GCRs. Paul Scherrer Institut
Wir schaffen Wissen heute für morgen Laboratory for Nuclear Materials Nuclear Energy and Safety Manuel A. Pouchon (PSI), 27.02.2015 Paul Scherrer Institut M.A. Pouchon, H.-M. Prasser, G. Perret, A. Pautz
More information2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea
HALDEN S IN-PILE TEST TECHNOLOGY FOR DEMONSTRATING THE ENHANCED SAFETY OF WATER REACTOR FUELS Margaret A. McGrath 1 1 OECD Halden Reactor Project, IFE: Os Alle 5/P.O. Box 173, 1751 Halden, Norway, Margaret.mcgrath@ife.no
More informationHTR reactors within Polish strategy of nuclear energy development Cooperation with Japan
HTR reactors within Polish strategy of nuclear energy development Cooperation with Japan Taiju SHIBATA Senior Principal Researcher Group Leader, International Joint Research Group HTGR Hydrogen and Heat
More informationSpecific Aspects of High Burnup or Mixed Oxide Fuel Rods during Dry Storage
Specific Aspects of High Burnup or Mixed Oxide Fuel Rods during Dry Storage Gerold Spykman TÜV NORD c/o TÜV NORD EnSys Hannover GmbH & Co. KG Department Reactor Technology and Fluid Mechanics Section Reactor
More informationREACTOR TECHNOLOGY DEVELOPMENT UNDER THE HTTR PROJECT TAKAKAZU TAKIZUKA
ELSEVIER www.elsevier.com/locate/pnucene Progress in Nuclear Energy; Vol. 47, No. 1-4, pp. 283-291,2005 Available online at www.sciencedirect.com 2005 Elsevier Ltd. All rights reserved s =, E N e E ~)
More informationFast Reactor Operating Experience in the U.S.
Fast Reactor Operating Experience in the U.S. Harold F. McFarlane Deputy Associate Laboratory Director for Nuclear Science and Technology www.inl.gov 3 March 2010 [insert optional photo(s) here] Thanks
More informationOverview and Progress of High Temperature Reactor Pebble-bed Module Demonstration Project (HTR-PM)
Overview and Progress of High Temperature Reactor Pebble-bed Module Demonstration Project (HTR-PM) FU Jian JIANG Yingxue CHENG Hongyong CHENG Wei (Huaneng Shandong Shidao Bay Nuclear Power Co., Ltd.) Abstract
More informationFuel Management Effects on Inherent Safety of Modular High Temperature Reactor
Journal of NUCLEAR SCIENCE and TECHNOLOGY, 26[7], pp. 647~654 (July 1989). 647 Fuel Management Effects on Inherent Safety of Modular High Temperature Reactor Yukinori HIROSEt, Peng Hong LIEM, Eiichi SUETOMI,
More informationMaintenance Concept for Modular Blankets in Compact Stellarator Power Plants
Maintenance Concept for Modular Blankets in Compact Stellarator Power Plants Siegfried Malang With contributions of Laila A. EL-Guebaly Xueren Wang ARIES Meeting UCSD, San Diego, January 8-10, 2003 Overview
More informationSafety Analysis Results of Representative DEC Accidental Transients for the ALFRED Reactor
FR13 - TECHNICAL SESSION 3.5: Fast reactor safety: post-fukushima lessons and goals for next-generation reactors Paper n. IAEA-CN-199/260 Safety Analysis Results of Representative DEC Accidental Transients
More informationEU Designs and Efforts on ITER HCPB TBM
EU Designs and Efforts on ITER HCPB TBM L.V. Boccaccini Contribution: S. Hermsmeyer and R. Meyder ITER TBM Project Meeting at UCLA February 23-25, 2004 UCLA, February 23rd, 2004 EU DEMO and TBM L.V. Boccaccini
More informationA STUDY ON THE STANDARD SYSTEM FOR HTGR POWER PLANTS
SMiRT-23, Paper ID 636 A STUDY ON THE STANDARD SYSTEM FOR HTGR POWER PLANTS ABSTRACT Lihong Zhang *, Fu Li, Yujie Dong, and Jingyuan Qu Institute Nuclear and New Energy Technology Collaborative Innovation
More informationA High Temperature Gas Loop to Simulate VHTR and Nuclear Hydrogen Production System
20th International Conference on Structural Mechanics in Reactor Technology (SMiRT 20) Espoo, Finland, August 9-14, 2009 SMiRT 20-Division 10, Paper 1870 A High Temperature Gas Loop to Simulate VHTR and
More informationHigh Temperature Gas Cooled Reactors
High Temperature Gas Cooled Reactors Frederik Reitsma Gas-Cooled Reactors Technology Nuclear Power Technology Development Section Division of Nuclear Power Department of Nuclear Energy 11th GIF-IAEA Interface
More informationANNEX XI. FIXED BED NUCLEAR REACTOR (FBNR) Federal University of Rio Grande do Sul (Brazil)
ANNEX XI FIXED BED NUCLEAR REACTOR (FBNR) Federal University of Rio Grande do Sul (Brazil) XI-1. General information, technical features, and operating characteristics XI-1.1. Introduction The Fixed Bed
More informationOperation of the helium cooled DEMO fusion power plant and related safety aspects
Operation of the helium cooled DEMO fusion power plant and related safety aspects 1 st IAEA workshop on Challenges for coolants in fast spectrum system: Chemistry and materials, Vienna, July, 5-7 2017
More informationScenarios of Heavy Beyond-Design-Basis Accidents in HTGRs N.G. Kodochigov, Yu.P. Sukharev
Scenarios of Heavy Beyond-Design-Basis Accidents in HTGRs N.G. Kodochigov, Yu.P. Sukharev IAEA Technical Meeting on the Safety of High Temperature Gas Cooled Reactors in the Light of the Fukushima Daiichi
More informationWorkgroup Thermohydraulics. The thermohydraulic laboratory
Faculty of Mechanical Science and Engineering Institute of Power Engineering Professorship of Nuclear Energy and Hydrogen Technology Workgroup Thermohydraulics The thermohydraulic laboratory Dr.-Ing. Christoph
More informationEngineering 2 (2016) Contents lists available at ScienceDirect. Engineering. journal homepage:
Engineering 2 (2016) 112 118 Contents lists available at ScienceDirect Engineering journal homepage: www.elsevier.com/locate/eng Research Nuclear Power Review The Shandong Shidao Bay 200 MW e High-Temperature
More information