Progress report on the Italian national program on fast reactors
|
|
- Julianna Hensley
- 6 years ago
- Views:
Transcription
1 Progress report on the Italian national program on fast reactors P.Agostini; G.Grasso; M.Angiolini ENEA L.Cinotti - Hydromine Vienna, May
2 Initiatives and collaborations to support LFR 2
3 FALCON consortium In december 2013 the FALCON (Fostering ALfred CONstruction) Consortium was signed among ANSALDO, ENEA and ICN (Romania): to support the contruction of ALFRED through EU structural funds to optimize the cooperation among the PARTIES through strategic, management, governance, financial and technical work In 2014 also CVRez (Czech Republic) adhered the FALCON consortium Several contacts were taken with Romania Government representatives to coordinate the access to European regional funds dedicated to South Muntenia Region In August 2014 the ALFRED Project was included in the draft of Smart Specialization Platform of South Muntenia region The FALCON agreement has been re-newed in June
4 FALCON consortium Recent updates within Falcon Consortium The political situation in Romania is in favor of ALFRED reactor In 2017 Romanian Ministry of Research has announced progressive funds availability for: Construction of Lead technology based preparatory infrastructures and laboratories (minor project) 90M Construction of ALFRED (major project) 700 M ENEA and ANSALDO assured all the support, by in-kind contribution, to write the technical specifications to launch the orders 4
5 Hydromine LFR concept Hydromine is an U.S. based company, very active in the business of energy and mining. It has recently hired a small group of Italian LFR specialists acquiring the rights on their LFR concept. The chief engineer is Luciano Cinotti, formerly ANSALDO, who based his concept mainly on ENEA technology Hydromine officially presented its concept in July 2016 at Imperial College, London. The Hydromine concept is reported in this presentation 5
6 Other LFR collaborations ENEA and Italian companies continue to collaborate with Chinese INEST Institute to CLEAR-S erection GEMMA ENEA started further collaborations on LFR technology with EU and outside EU companies In 2017 a new 4 Meuro EU project, aiming at Gen IV materials, was approved for funding. The project name is GEMMA (GEneration IV Materials Maturity), the coordinator is ENEA. The partnership includes 22 European Institutes + KAERI 6
7 LFR-AS-200 7
8 The Hydromine LFR-AS-200 LFR stands for Lead-cooled Fast Reactor, AS stands for Amphora-Shaped, referring to the shape of the Inner Vessel 200 is the rated electrical power of the reactor in MW. The LFR-AS-200 is based on innovative solutions conceived by the Hydromine team in the last ten years and presented for the first time on July 2016 in London at the Imperial College. Core power (MWth) 480 Electrical power (MWe) 200 Core inlet/outlet T ( C) 420/530 Primary loop pressure loss (bar) 1,3 Table1: Main design parameters of LFR-AS- 200 Secondary cycle Superheated steam Turbine inlet pressure (bar) 180 Feed water /steam temperature ( C) 340/500 L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 8
9 LFR-AS-200, 10 years work for achieving a simple, consistent design LFR-AS-200 is predictably economic Volume of the primary system < 1m 3 /MWe!! ~ 4 times less than SPX1 ~ 2-3 times less than the best SFR projects ~ 3-5 time less than previous LFR projects LFR-AS-200 is feasible Height of the reactor vessel 6,2m!! L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 9
10 The SG of LFR-AS-200 differs from current technology From: long SG deeply immersed in the melt with top inlet window and bottom outlet window. To: short Spiral-tube SG partially raised with respect to the cold collector free level with bottom inlet and top outlet. Advantages: - No risk of steam release deep in the melt and large lead displacements. - No risk of cover gas entrance into the core. - Short, compact SG, reduced RV height. - No Deversoir, reduced RV diameter. L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 10
11 The Pump assembly differs from current technology From: Pumps in the cold collector, in-between the SGs, with long shafts and in-melt bearings. To: Pump in the hot collector, integrated in each SG to feed the SG, with large hollow shaft filled with lead, and no in-melt bearings. Advantages: - Use of available space inside the SG, reduced RV diameter. - No bearings in lead. - High mechanical inertia for mild transients from forced to natural circulation. - Core fed by the hydrostatic head Δh between cold and hot collector, no LIPOSO L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 11
12 The issue of refueling the LFR. Refueling is difficult in sodium: - Both Jōyō and Monju in Japan are at shutdown because of handling accidents. - Need of a complicate in-vessel refueling machine. - Need of complicate preparatory interventions. In-lead refueling is even more difficult: - Higher refueling temperature. - Large buoyance effect. Above Core Structure to be moved for refueling L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 12
13 The Fuel Assembly of LFR-AS-200 differs from current technology From: Fuel Assemblies immersed in the melt handled by an in-vessel + ex-vessel Refueling Machine. To: Fuel Assemblies with stem extended above the lead free level handled by an ex-vessel Refueling Machine. Advantages: - No in-vessel Refueling Machine, reduced RV diameter. - No Above Core Structure, reduced RV diameter. - Buoyance compensated by the emerged portion of the stem. - Increased reliability. A cold handle allows easy handling in hot oil. L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 13
14 The issue of ISI of the core support system The classical core support structures, Diagrid and Strongback, are critical components subjected to thermal transients and neutron damage. Their collapse could bring about effects of control rod extraction. Their ISI is difficult in sodium because of deep location and complexity. Their ISI in lead would be even more difficult. L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 14
15 The Core of the FR-AS-200 is self-sustaining From: Fuel Assemblies (FA) supported in lead at the bottom by Diagrid and Strongback. To: Core anchored at the top to a barrel in gas space. Advantages: - No Diagrid. - No Strongback. - No support system subject to thermal transients and neutron damage (only disc cams integral part of the FAs). - No need of disconnecting all FAs instrumentation at refueling. - Increased availability. Cams L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 15
16 The Amphora-Shaped Inner Vessel From: Inner Vessel, large at top and smaller at bottom, containing Shielding Assemblies (and Breeding Assemblies). To: Amphora-Shaped Inner Vessel, no Shielding Assemblies (and no Breeding Assemblies). Advantages: - No need of Shielding Assemblies, reduced RV diameter, increased availability, reduced waste inventory. L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 16
17 The ex-core control rods From: In-core control and shut down rods. To: Ex-core control and shut down rods. Advantages: - Reduced core dimensions. - No disconnection of rod drives for refueling. L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 17
18 Resistance to cyber attacks Logics and operators backed up by passively actuated systems to shut down the reactor. In a LFR there is a margin of hundreds K between the operating temperature and the safety limit, hence, e.g., thermal expansion can be used to open the core and shut down the reactor in case of failure of logics or of operator intervention. Bi-metallic expansors open and shut down the core when temperature exceeds normal operating limits. L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 18
19 Resistance to cyber attacks 2/2 Passive shut down is complemented by two independent, passive, diverse, redundant DHR systems to face the Unprotected Loss Of Offsite Power (ULOOP). DHR1:Three water-steam loops passively operated with water as heat sink. DHR2: Three lead loops passively actuated and operated with air as heat sink. Chimney Louvers Air cooler Lead loop d Lead-water, double-wall bayonet-tube bundle heat exchanger at Brasimone site. Thermal expansion of the cold leg of the lead loop opens the louvers of the air coolers when lead temperature exceeds 400 C. L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 19
20 Conclusion 1 LFR-AS-200 enhances safety while dispensing of hitherto classical critical components Components/systems no more needed Rationale for elimination Impact Intermediate loop Lead properties. Compact Reactor Building, easy operation, cost reduction (about 30% of the cost of NSSS in a SFR). Above core structure Use of FAs with extended Reduced diameter of the RV, no need stem. of its displacement for refuelling. In-vessel refuelling machine Use of FAs with extended stem. Elimination of a mechanically critical component to be operated in opaque medium. Reduced diameter of the RV, reduced vibration risk. Deversoir or equivalent component SG-outlet window at top of the SG. Diagrid Self-sustaining core. No need of a component difficult to inspect. Strongback Core supported by the roof via the barrel. No need of a component difficult to inspect. No structure fixed to the RV LIPOSO, hydraulic connection pump to diagrid Pumps in the hot collector. Elimination of a mechanically critical component. Pump bearings in lead Low required NPSH for the pumps. Elimination of a mechanically critical component. Flywheel on the pump system Use of rotating lead inertia. Smaller footprint on the reactor roof. Core shielding assemblies Use of the ASIV. Reduced diameter of the RV, simplicity. Blanket assemblies No net Pu generation. Reduced diameter of the RV, simplicity, increased proliferation resistance. L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project 20
21 Materials studies 21
22 GEMMA GEMMA Project Challenge: resolving the key remaining issues regarding structural (and fuel materials) to be used in Generation-IV reactor concepts under consideration in the EU Keywords: materials and joints under neutron irradiation, high temperature, compatibility with coolants (and advanced fuels), physical models and/or modelling-oriented experiments, microstructural change and effects on material properties, advanced micro-structural characterisation techniques, mitigation strategies surface engineering concepts Impact: predictive capability, design codes, overcome bottlenecks of certification of materials, contribute to safety improvements also in other nuclear systems 22
23 GEMMA Proposed structure focus on 316L(N) & 15/15Ti Proposed structure focus on 316L(N) & 15/15Ti LFR, GFR WP1-Surface engineering & its basic characterisation A.Weisenburgerr MITIGATION Base material selection and procurement SFR, LFR (GFR) WP2-Welding & its relevant characterisation K.Tucek DESIGN RULES SFR (LFR, GFR) WP3-Irradiation effects: modelling and experiments M.Nastar MODELLING & µstructure DESIGN RULES LFR, GFR WP4-Compatibility with high T coolant: Corrosion/erosion testing & modelling E. Stergar MODELLING & µstructure WP5-Coordination and dissemination (communication & exploitation of results) P. Agostini 23
24 GEMMA Support to MYRRHA Corrosion tests in LBE of AISI 316L, AISI316LN and 15-15Ti MYRRHA, Corrosion of: welded joints of above steels by TIG & SAW, AFA steels and coated steels. Mechanical qualifications in LBE of the above steels by: SSRT, fracture toughness, creep rupture Corrosion modeling in HLM Lead-Bismuth coolant 24
25 GEMMA Support to ALFRED Corrosion tests in Pb of AISI 316L, AISI316LN and 15-15Ti ALFRED, Corrosion of: welded joints of above steels by TIG & SAW, AFA steels and coated steels. Mechanical qualifications in Lead of the above steels by: SSRT, fracture toughness, creep rupture Corrosion modeling in HLM 25
26 GEMMA Support to ASTRID Theoretical studies, models and tests of diffusion aging by annealing and ion irradiation in Fe-Ni-Cr systems. Detailed qualification of large thickness AISI 316LN welds through measurement of residual stresses by neutron diffraction and modelling 26
27 GEMMA Support to ALLEGRO Mechanical qualification at 550C of AISI 316L welded joints by TIG and SAW: SSRT Fracture toughness Creep rupture Mechanical qualification at 550C of AISI 316L Al2O3 coated SSRT Creep Rupture Swelling qualification under ion irradiation of coated AISI 316L Low damage qualification under neutron irradiation of coated AISI 316L 27
28 Conclusions Recent changes in the Romanian political situation offered important chances to fund the ALFRED initiative In the frame of FALCON consortium. This new fact is boosting the LFR activities by ENEA and ANSALDO as well. Hydromine US based company has recently acquired rights for an innovative LFR by an Italian group of engineers and designers formerly in ANSALDO. The Hydromine project LFR-AS-200 presents innovative design features and relies on technologies developed by ENEA ENEA coordinates a new EU project focused on structural materials for GEN IV reactors. The project includes 22 research institutes and industries from: Italy, Belgium, Germany, France, Finland, U.K., Spain, Czech Republic, Sweden, Poland, Romania and Korea. The ongoing international collaborations by ENEA and ANSALDO are: in the European frame with Romanian ICN and Czech CVRez with Chinese Academy of Sciences with US companies with Russian institutes 28
Analysis of Unprotected Transients in the Lead-Cooled ALFRED Reactor
Analysis of Unprotected Transients in the Lead-Cooled ALFRED Reactor G. Bandini (ENEA/Bologna) E. Bubelis, M. Schikorr (KIT/Karlsruhe) A. Alemberti, L. Mansani (Ansaldo Nucleare/Genova) Consultants Meeting:
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 informationEvolution of Nuclear Energy Systems
ALLEGRO Project 2 Evolution of Nuclear Energy Systems 3 General objectives Gas cooled fast reactors (GFR) represent one of the three European candidate fast reactor types. Allegro Gas Fast Reactor (GFR)
More informationGIF Lead-cooled Fast Reactor Development Status Alessandro Alemberti (EURATOM / Ansaldo Nucleare)
GIF Lead-cooled Fast Reactor Development Status Alessandro Alemberti (EURATOM / Ansaldo Nucleare) on behalf of GIF LFR provisional System Steering Committee 10th GIF-IAEA Interface Meeting IAEA Headquarters,
More informationSodium Fast Reactors Systems and components (Part 2)
IAEA Education &Training Seminar on Fast Reactor Science and Technology CNEA Bariloche, Argentina October 1 5, 2012 Sodium Fast Reactors Systems and components (Part 2) Dr. Christian LATGE Nuclear Technology
More informationModule 05 WWER/ VVER (Russian designed Pressurized Water Reactors)
Module 05 WWER/ VVER (Russian designed Pressurized Water Reactors) 1.3.2016 Prof.Dr. Böck Technical University Vienna Atominstitut Stadionallee 2, 1020 Vienna, Austria ph: ++43-1-58801 141368 boeck@ati.ac.at
More informationBN-1200 Reactor Power Unit Design Development
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) BN-1200 Reactor Power Unit Design Development B.A. Vasilyev a, S.F. Shepelev a, M.R.
More informationLast Twenty Years Experiences with Fast Reactor in Japan. Kazumoto Ito and Tsutomu Yanagisawa Japan Atomic Energy Agency (JAEA)
Last Twenty Years Experiences with Fast Reactor in Japan Kazumoto Ito and Tsutomu Yanagisawa Japan Atomic Energy Agency (JAEA) 1 Fast Reactor Winter FBR project terminations - The U.S.: Clinch River Breeder
More informationConcepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant
8 Concepts and Features of ATMEA1 TM as the latest 1100 MWe-class 3-Loop PWR Plant KOZO TABUCHI *1 MASAYUKI TAKEDA *2 KAZUO TANAKA *2 JUNICHI IMAIZUMI *2 TAKASHI KANAGAWA *3 ATMEA1 TM is a 3-loop 1100
More informationOverview of the IAEA and Fast Reactor Activities
Education and Training Seminar on FAST REACTOR SCIENCE AND TECHNOLOGY Centro Atòmico Bariloche, October 1 5, 2012 Overview of the and Fast Reactor Activities Stefano Monti Team Leader Fast Reactor Technology
More informationDesign and Safety Aspect of Lead and Lead-Bismuth Cooled Long-Life Small Safe Fast Reactors for Various Core Configurations
Journal of NUCLEAR SCIENCE and TECHNOLOGY, 32[9], pp. 834-845 (September 1995). Design and Safety Aspect of Lead and Lead-Bismuth Cooled Long-Life Small Safe Fast Reactors for Various Core Configurations
More informationNuScale Power Modular and Scalable Reactor. NuScale. Integral Pressurized Water Reactor. Light Water. Light Water.
NuScale Power Modular and Scalable Reactor Overview Full Name NuScale Power Modular and Scalable Reactor Acronym NuScale Reactor type Integral Pressurized Water Reactor Coolant Light Water Moderator Light
More informationCFD Analysis of Decay Heat Removal Scenarios of the Lead cooled ELSY reactor. Michael Böttcher
CFD Analysis of Decay Heat Removal Scenarios of the Lead cooled ELSY reactor Michael Böttcher Institut für Neutronenphysik und Reaktortechnik (INR), Karlsruher Institut für Technologie, KIT Abstract In
More informationSmall Modular Reactor Materials R&D Program Materials Coordination Webinar
Small Modular Reactor Materials R&D Program Materials Coordination Webinar William Corwin Office of Advanced Reactor Technologies U.S. Department of Energy August 2012 SMRs Are Strong Contenders to Augment
More informationThe Westinghouse Advanced Passive Pressurized Water Reactor, AP1000 TM. Roger Schène Director,Engineering Services
The Westinghouse Advanced Passive Pressurized Water Reactor, AP1000 TM Roger Schène Director,Engineering Services 1 Background Late 80: USA Utilities under direction of EPRI and endorsed by NRC : Advanced
More informationLFR core design. for prevention & mitigation of severe accidents
LFR core design for prevention & mitigation of severe accidents Giacomo Grasso UTFISSM Technical Unit for Reactor Safety and Fuel Cycle Methods Coordinator of Core Design Work Package in the EURATOM FP7
More informationThe Lead-cooled Fast Reactor: Status Report for 2012 GIF Symposium
The Lead-cooled Fast Reactor: Status Report for 2012 GIF Symposium Alessandro Alemberti Ansaldo Nucleare Chairman, GIF-LFR-PSSC Valeriy Smirnov NIKIET, Moscow Member GIF-LFR-PSSC Craig F. Smith Naval Postgraduate
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 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 informationCAREM Prototype Construction and Licensing Status
IAEA-CN-164-5S01 CAREM Prototype Construction and Licensing Status H. Boado Magan a, D. F. Delmastro b, M. Markiewicz b, E. Lopasso b, F. Diez, M. Giménez b, A. Rauschert b, S. Halpert a, M. Chocrón c,
More informationLEAD-COOLED FAST-NEUTRON REACTOR BREST. Yu.G. Dragunov, V.V. Lemekhov, A.V. Moiseyev, V.S. Smirnov (NIKIET, Moscow, Russia)
LEAD-COOLED FAST-NEUTRON REACTOR BREST Yu.G. Dragunov, V.V. Lemekhov, A.V. Moiseyev, V.S. Smirnov (NIKIET, Moscow, Russia) Large-scale nuclear power based on fast-neutron reactors operating in a closed
More informationNSSS Design (Ex: PWR) Reactor Coolant System (RCS)
NSSS Design (Ex: PWR) Reactor Coolant System (RCS) Purpose: Remove energy from core Transport energy to S/G to convert to steam of desired pressure (and temperature if superheated) and moisture content
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 informationCAREM: AN INNOVATIVE-INTEGRATED PWR
18th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18) Beijing, China, August 7-12, 2005 SMiRT18-S01-2 CAREM: AN INNOVATIVE-INTEGRATED PWR Rubén MAZZI INVAP Nuclear Projects
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 informationWestinghouse Small Modular Reactor. Passive Safety System Response to Postulated Events
Westinghouse Small Modular Reactor Passive Safety System Response to Postulated Events Matthew C. Smith Dr. Richard F. Wright Westinghouse Electric Company Westinghouse Electric Company 600 Cranberry Woods
More informationLECOTELO INSTALLATION USED FOR CORROSION/EROSION TESTING OF STRUCTURAL MATERIALS IN MOLTEN LEAD
U.P.B. Sci. Bull., Series C, Vol. 79, Iss. 1, 2017 ISSN 2286-3540 LECOTELO INSTALLATION USED FOR CORROSION/EROSION TESTING OF STRUCTURAL MATERIALS IN MOLTEN LEAD Virgil COJOCARU 1, Ilie PRISECARU 2, Nicolae
More informationFrench R&D program on SFR and the
PRESENT STATUS OF FRENCH PROGRAM ASTRID JAPAN FRANCE COOPERATION EXPECTATIONS ON MONJU MONJU ASTRID ALAIN PORRACCHIA DIRECTOR FOR INNOVATION AND INDUSTRIAL SUPPORT CEA/DEN French R&D program on SFR and
More informationEFIT: THE EUROPEAN FACILITY FOR INDUSTRIAL TRANSMUTATION OF MINOR ACTINIDES. II.A. Core
EFIT: THE EUROPEAN FACILITY FOR INDUSTRIAL TRANSMUTATION OF MINOR ACTINIDES Barbensi Andrea a, Corsini Giovanni a, Mansani Luigi a, Artioli Carlo b, Glinatsis Georgios b a Ansaldo Nucleare S.p.A., Corso
More informationFast reactor development and worldwide cooperation in Generation-IV International Forum
Fast reactor development and worldwide cooperation in Generation-IV International Forum FR13 Paris, France March 4, 2013 Yutaka Sagayama Former Chair of the Generation-IV International Forum Senior Advisor
More informationGraded approach practices for the mechanical components of French research reactor projects
Graded approach practices for the mechanical components of French research reactor projects Claude PASCAL RMR/RR Rabat IAEA conference, november 2011 Content Context Classification of SSCs Associated Requirements
More informationPassive Cooldown Performance of Integral Pressurized Water Reactor
Energy and Power Engineering, 2013, 5, 505-509 doi:10.4236/epe.2013.54b097 Published Online July 2013 (http://www.scirp.org/journal/epe) Passive Cooldown Performance of Integral Pressurized Water Reactor
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 informationSFR System Status and Plans
SFR System Status and Plans Dohee Hahn SFR SSC Chair GIF Symposium San Diego November 15-16, 2012 Outline Overview of SFR R&D Key Priority Objectives Project Status Application of GIF Methodologies Challenging
More informationDesign Code Development in EERA JPNM: work done and future needs
Design Code Development in EERA JPNM: work done and future needs MatISSE/JPNM workshop on cross-cutting issues in structural materials R&D for future energy systems 25-26 November 2015, Petten, NL K-F
More informationNuclear Power A Journey of Continuous Improvement
Nuclear Power A Journey of Continuous Improvement Westinghouse Non Proprietary Class 3 Our Place in Nuclear History Innovation 1886 and forever Implementation & Improvement 1957 through Today Renaissance
More informationGas-cooled Fast Reactor Status and program. Pascal ANZIEU Commissariat à l énergie atomique Atomic Energy Commission France
Gas-cooled Fast Reactor Status and program Pascal ANZIEU Commissariat à l énergie atomique Atomic Energy Commission France Nuclear Energy Division P. Anzieu - GFR Status 1 GFR: an alternative Fast Neutrons
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 informationSustainable Nuclear Energy technology Platform: SNETP. Deployment strategy: DS 2015
Sustainable Nuclear Energy technology Platform: SNETP Deployment strategy: DS 2015 Task force coordinated by Marylise Caron-Charles Status on July 8, 2015 NEA workshop on Nuclear Innovation roadmap 1 Purpose
More informationRELAP5/MOD3.2 INVESTIGATION OF A VVER-440 STEAM GENERATOR HEADER COVER LIFTING
Science and Technology Journal of BgNS, Vol. 8, 1, September 2003, ISSN 1310-8727 RELAP5/MOD3.2 INVESTIGATION OF A VVER-440 STEAM GENERATOR HEADER COVER LIFTING Pavlin P. Groudev, Rositsa V. Gencheva,
More informationOverviewof Gen IV Reactor Systems Development
Overviewof Gen IV Reactor Systems Development Status by project 2 Generation IV GFR - Summary Helium coolant Fast neutron spectrum High outlet temperature Longer term alternative to SFR + Transparent coolant
More informationEXPERIMENTS ON THE PERFORMANCE SENSITIVITY OF THE PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF AN ADVANCED INTEGRAL TYPE REACTOR
EXPERIMENTS ON THE PERFORMANCE SENSITIVITY OF THE PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF AN ADVANCED INTEGRAL TYPE REACTOR HYUN-SIK PARK *, KI-YONG CHOI, SEOK CHO, SUNG-JAE YI, CHOON-KYUNG PARK and MOON-KI
More informationU.S. Department of Energy Advanced Reactor Research and Development Program for Fast Reactors
資料 1 U.S. Department of Energy Advanced Reactor Research and Development Program for Fast Reactors John W. Herczeg Deputy Assistant Secretary for Nuclear Technology Research and Development Office of Nuclear
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 informationOverview of PbBi cooled Reactor development and ADS Program in China
C-13 Overview of PbBi cooled Reactor development and ADS Program in China Presented by Y.BAI Contributed by FDS Team Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences Institute
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 informationSystem Analysis of Pb-Bi Cooled Fast Reactor PEACER
OE-INES-1 International Symposium on Innovative Nuclear Energy Systems for Sustainable Development of the World Tokyo, Japan, October 31 - November 4, 2004 System Analysis of Pb-Bi ooled Fast Reactor PEAER
More informationSafety Design Requirements and design concepts for SFR
Safety Design Requirements and design concepts for SFR Reflection of lessons learned from the Fukushima Dai-ichi accident Advanced Nuclear System Research & Development Directorate Japan Atomic Energy
More informationEPR: Steam Generator Tube Rupture analysis in Finland and in France
EPR: Steam Generator Tube Rupture analysis in Finland and in France S. ISRAEL Institut de Radioprotection et de Sureté Nucléaire BP 17 92262 Fontenay-aux-Roses Cedex, France Abstract: Different requirements
More informationGENERATION IV NUCLEAR ENERGY SYSTEMS
GENERATION IV NUCLEAR ENERGY SYSTEMS HOW THEY GOT HERE AND WHERE THEY ARE GOING David J. Diamond Brookhaven National Laboratory Energy Sciences and Technology Department Nuclear Energy and Infrastructure
More informationWestinghouse SMR & Nuclear Fuel Overview
Westinghouse SMR & Nuclear Fuel Overview Carlos Leipner, Westinghouse VP Latin America Presented at LAS-ANS July 2014 Rio de Janeiro, Brasil 2014 Westinghouse Electric Company LLC, All Rights Reserved.
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 informationSafety Implication for Gen-IV SFR based on the Lesson Learned from the Fukushima Dai-ichi NPPs Accident. Ryodai NAKAI Japan Atomic Energy Agency
Safety Implication for Gen-IV SFR based on the Lesson Learned from the Fukushima Dai-ichi NPPs Accident Ryodai NAKAI Japan Atomic Energy Agency Contents Introduction Japanese Government Report to the IAEA
More informationDesign, Safety Technology and Operability Features of Advanced VVERs
Technical Cooperation Project INT/4/142 Interregional Workshop on Advanced Nuclear Reactor Technology for Near Term Deployment IAEA Headquarters, Vienna, Austria, 4-8 July 2011 Design, Safety Technology
More informationCurrent Status and Future Challenges of Innovative Reactors Development in Japan
Innovation for Cool Earth Forum 2017, Tokyo, Japan, October 4-5, 2017 Current Status and Future Challenges of Innovative Reactors Development in Japan 5 October, 2017 Yutaka Sagayama Assistant to the President
More informationLead cooled Fast SMR s: (S)STAR, ENHS and ELSY
Lead cooled Fast SMR s: (S)STAR, ENHS and ELSY Craig F. Smith LLNL Chair Professor Naval Postgraduate School The 4th Annual Asia Pacific Nuclear Energy Forum on Small and Medium Reactors (SMRs): Benefits
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 informationThe ESBWR an advanced Passive LWR
1 IAEA PC-Based Simulators Workshop Politecnico di Milano, 3-14 October 2011 The ES an advanced Passive LWR Prof. George Yadigaroglu, em. ETH-Zurich and ASCOMP yadi@ethz.ch 2 Removal of decay heat from
More informationPiping Technology. High Pressure Piping Systems. for power plants
Piping Technology High Pressure Piping Systems for power plants High Pressure Piping Systems for power plants Advice and Project management Expert advice to our customers is the bedrock of the growing
More informationRELAP 5 ANALYSIS OF PACTEL PRIMARY-TO-SECONDARY LEAKAGE EXPERIMENT PSL-07
Fifth International Seminar on Horizontal Steam Generators 22 March 21, Lappeenranta, Finland. 5 ANALYSIS OF PACTEL PRIMARY-TO-SECONDARY LEAKAGE EXPERIMENT PSL-7 József Bánáti Lappeenranta University of
More informationNUCLEAR ENERGY MATERIALS AND REACTORS Vol. I - Pressurized Water Reactors - J. Pongpuak
PRESSURIZED WATER REACTORS J. Pongpuak Department of Chemical Engineering, University of New Brunswick, Canada Keywords: Pressurized Water Reactors, Reactor Core, Fuel Elements, Control Rods, Steam Generators
More informationBalance of Plant Requirements and Concepts for Tokamak Reactors
Balance of Plant Requirements and Concepts for Tokamak Reactors Edgar Bogusch EFET / Framatome ANP GmbH 9 th Course on Technology of Fusion Tokamak Reactors Erice, 26 July to 1 August 2004 1 Contents Introduction
More informationNatural Circulation Level Optimization and the Effect during ULOF Accident in the SPINNOR Reactor
Natural Circulation Level Optimization and the Effect during ULOF Accident in the SPINNOR Reactor Ade Gafar Abdullah 1,2,*, Zaki Su ud 2, Rizal Kurniadi 2, Neny Kurniasih 2, Yanti Yulianti 2,3 1 Electrical
More informationCOLD NEUTRON SOURCE AT CMRR
COLD NEUTRON SOURCE AT CMRR Hu Chunming Shen Wende, Dai Junlong, Liu Xiankun ( 1 ) Vadim Kouzminov, Victor Mityukhlyaev / 2 /, Anatoli Serebrov, Arcady Zakharov ( 3 ) ABSTRACT As an effective means to
More informationSmall Reactors R&D in China. ZHENG Mingguang Ph D Presented on the meeting of TWG-LWR June 18 th -20 th 2013 IAEA, Vienna
Small Reactors R&D in China ZHENG Mingguang Ph D Presented on the meeting of TWG-LWR June 18 th -20 th 2013 IAEA, Vienna CONTENT 1 Introduction of SMR 2 CAP150 developed by SNERDI/SNPTC 3 CAP FNPP developed
More informationBARC BARC PASSIVE SYSTEMS RELIABILITY ANALYSIS USING THE METHODOLOGY APSRA. A.K. Nayak, PhD
BARC PASSIVE SYSTEMS RELIABILITY ANALYSIS USING THE METHODOLOGY APSRA A.K. Nayak, PhD Reactor Engineering Division Bhabha Atomic Research Centre Trombay, Mumbai 400085, India INPRO Consultancy Meeting
More informationVerification of the MELCOR Code Against SCDAP/RELAP5 for Severe Accident Analysis
Verification of the Code Against SCDAP/RELAP5 for Severe Accident Analysis Jennifer Johnson COLBERT 1* and Karen VIEROW 2 1 School of Nuclear Engineering, Purdue University, West Lafayette, Indiana 47907-2017,
More informationGT-MHR OVERVIEW. Presented to IEEE Subcommittee on Qualification
GT-MHR OVERVIEW Presented to IEEE Subcommittee on Qualification Arkal Shenoy, Ph.D Director, Modular Helium Reactors General Atomics, San Diego April 2005 Shenoy@gat.com GT-MHR/LWR COMPARISON Item GT-MHR
More informationA Research Reactor Simulator for Operators Training and Teaching. Abstract
Organized and hosted by the Canadian Nuclear Society. Vancouver, BC, Canada. 2006 September 10-14 A Research Reactor Simulator for Operators Training and Teaching Ricardo Pinto de Carvalho and José Rubens
More informationAugust 24, 2011 Presentation to Colorado School of Mines
HEAVY-METAL NUCLEAR POWER: Could Reactors Burn Radioactive Waste to Produce Electric Power and Hydrogen? Eric P. Loewen, Ph.D. President, American Nuclear Society August 24, 2011 Presentation to Colorado
More informationTHERMAL AND STRESS ANALYSIS OF HYPER TARGET SYSTEM *
THERMAL AND STRESS ANALYSIS OF HYPER TARGET SYSTEM * T.Y. Song, N.I. Tak, W.S. Park Korea Atomic Energy Research Institute P.O. Box 105 Yusung, Taejon, 305-600, Republic of Korea J.S. Cho, Y.S. Lee Department
More informationModule 06 Boiling Water Reactors (BWR)
Module 06 Boiling Water Reactors (BWR) 1.10.2015 Prof.Dr. Böck Vienna University oftechnology Atominstitute Stadionallee 2 A-1020 Vienna, Austria ph: ++43-1-58801 141368 boeck@ati.ac.at Contents BWR Basics
More informationTools and applications for core design and shielding in fast reactors
Technical Meeting on Liquid Metal Reactor Concepts: Core Design and Structural Materials, June 12-14, 2013 Tools and applications for core design and shielding in fast reactors Presented by: Reuven Rachamin
More informationMEXT Nuclear Energy R&D
Tokyo, 1 th November 2011 MEXT Nuclear Energy R&D Masaaki NISHIJO Director, Office for Nuclear Fuel Cycles, Ministry of Education, Culture, Sports, Science and Technology (MEXT) 1 Future Nuclear Energy
More informationMaterials Challenges for the Supercritical Water-cooled Reactor (SCWR)
Materials Challenges for the Supercritical Water-cooled Reactor (SCWR) http://ottawapolicyresearch.ca sbaindur@ottawapolicyresearch.ca CNS 2007 Saint John, NB. Outline of Talk Introduction Talk aimed at
More informationJoint ICTP-IAEA School of Nuclear Energy Management August 2011
2257-23 Joint ICTP-IAEA School of Nuclear Energy Management 8-26 August 2011 Nuclear Applications Fundamentals: Materials for fission and fusion technology Danas Ridikas IAEA, Vienna Austria Lecture 3
More informationThe risk of reactor pressure vessel material degradation Doel-3/Tihange-2
The risk of reactor pressure vessel material degradation Doel-3/Tihange-2 Ilse Tweer NURIS 2015, Vienna, 16-17 April 2015 Reactor pressure vessel structural integrity The reactor pressure vessel (RPV)
More informationGeneration IV Reactors
Generation IV Reactors Richard Stainsby National Nuclear Laboratory Recent Ex-Chair of the GFR System Steering Committee Euratom member of the SFR System Steering Committee What are Generation IV reactors?
More informationGAS-COOLED FAST REACTORS DHR SYSTEMS, PRELIMINARY DESIGN AND THERMAL- HYDRAULIC STUDIES
GAS-COOLED FAST REACTORS DHR SYSTEMS, PRELIMINARY DESIGN AND THERMAL- HYDRAULIC STUDIES J.Y. MALO *, C. BASSI, T. CADIOU, M. BLANC, A. MESSIÉ 1, A. TOSELLO and P. DUMAZ CEA/DEN/DER/SESI, CEA Cadarache
More informationSmall Modular Reactors: A Call for Action
Small Modular Reactors: A Call for Action Overview of Five SMR Designs by Dr. Regis A. Matzie Executive Consultant Adapted May 2015 for the Hoover Institution's Reinventing Nuclear Power project from a
More informationApplication for Permission to Extend the Operating Period and Application for Approval of Construction Plans of Unit 3 at Mihama Nuclear Power Station
November 26, 2015 The Kansai Electric Power Co., Inc. Application for Permission to Extend the Operating Period and Application for Approval of Construction Plans of Unit 3 at Mihama Nuclear Power Station
More informationSeismic isolation of LFR Reactor Buildings
EC Collaborative Project SILER: Seismic-Initiated events risk mitigation in LEad-cooled Reactors International Workshop 2013 Seismic isolation of LFR Reactor Buildings Ing. Giuseppe Moretti Ing. Ulisse
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 informationPreparedness at PFBR Kalpakkam to meet the challenges due to Natural events Prabhat Kumar, Project Director, PFBR, Director construction BHAVINI
BHARATIYA NABHIKIYA VIDYUT NIGAM LIMITED (A Government of India Enterprise) Preparedness at PFBR Kalpakkam to meet the challenges due to Natural events Prabhat Kumar, Project Director, PFBR, Director construction
More informationSmall and Modular Reactor Development, Safety and Licensing in Korea
Small and Modular Reactor Development, Safety and Licensing in Korea IAEA TWG-LWR Vienna, June 18-20, 2013 Presented by Jong-Tae Seo 1 Outline I. SMR Development in Korea II. SMART Development III. SMART
More informationImportance of materials for sustainable nuclear energy
Common EESC-EERA Event / EUSEW 2012 Brussels, 18 June 2012 Importance of materials for sustainable nuclear energy L. Malerba - SCK CEN Joint Programme Nuclear Materials SubProgramme coordinator (on behalf
More informationImplementation of Lessons Learned from Fukushima Accident in CANDU Technology
e-doc 4395709 Implementation of Lessons Learned from Fukushima Accident in CANDU Technology Greg Rzentkowski Director General, Power Reactor Regulation Canadian Nuclear Safety Commission on behalf of CANDU
More informationNuclear Reactor Types. An Environment & Energy FactFile provided by the IEE. Nuclear Reactor Types
Nuclear Reactor Types An Environment & Energy FactFile provided by the IEE Nuclear Reactor Types Published by The Institution of Electrical Engineers Savoy Place London WC2R 0BL November 1993 This edition
More informationNUCLEAR POWER NEW NUCLEAR POWER PLANTS IN 2012
NUCLEAR POWER NEW NUCLEAR POWER PLANTS IN 2012 AP1000 IN FEBRUARY 2012, THE FIRST NUCLEAR POWER PLANTS IN THE US IN 35 YEARS WERE LICENSCED TO BEGIN CONSTRUCTION. TWO WESTINGHOUSE AP1000 NUCEAR REACTOR
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 informationExperiments Carried-out, in Progress and Planned at the HTR-10 Reactor
Experiments Carried-out, in Progress and Planned at the HTR-10 Reactor Yuliang SUN Institute of Nuclear and New Energy Technology, Tsinghua University Beijing 100084, PR China 1 st Workshop on PBMR Coupled
More informationWestinghouse AP1000. Reactor
Westinghouse AP1000 A Third Generation Nuclear Reactor International Council on Systems Engineering (INCOSE) September 18, 2013 Andrew Drake, PMP Director, AP1000 Engineering Completion Engineering, Equipment
More informationNPP Simulators Workshop for Education - Passive PWR NPP & Simulator Overview
NPP Simulators Workshop for Education - Passive PWR NPP & Simulator Overview Wilson Lam (wilson@cti-simulation.com) CTI Simulation International Corp. www.cti-simulation.com Sponsored by IAEA Modified
More informationSUPER-SAFE, SMALL AND SIMPLE REACTOR (4S, TOSHIBA DESIGN)
SUPER-SAFE, SMALL AND SIMPLE REACTOR (4S, TOSHIBA DESIGN) Toshiba Corporation and Central Research Institute of Electric Power Industry (CRIEPI), Japan Overview Full name Super-Safe, Small and Simple Reactor
More informationBest practices for preparing vessel internals segmentation projects
Best practices for preparing vessel internals segmentation projects Joseph BOUCAU a*, Per SEGERUD b, Moisés SANCHEZ c a Westinghouse Electric Company, 43 rue de l Industrie, 1400 Nivelles, Belgium b Westinghouse
More informationDESIGN AND FABRICATION OF SERPENTINE TUBE TYPE SODIUM TO AIR HEAT EXCHANGERS FOR PFBR SGDHR CIRCUITS
DESIGN AND FABRICATION OF SERPENTINE TUBE TYPE SODIUM TO AIR HEAT EXCHANGERS FOR PFBR SGDHR CIRCUITS Aravinda Pai, T.K.Mitra, T. Loganathan and Prabhat Kumar Prototype Fast Breeder Reactor Project Bharatiya
More informationAdvanced Design of Mitsubishi PWR Plant for Nuclear Renaissance
Advanced Design of Mitsubishi PWR Plant for Nuclear Renaissance October 28, 2009 Etsuro SAJI General Manager, Reactor Core Engineering Department Mitsubishi Heavy Industries, Ltd. GEN-HSW-9102-0 Contents
More informationDevelopment of Welding and Hardfacing Technology: challenges for ASTRID project
Development of Welding and Hardfacing Technology: challenges for ASTRID project Sophie Dubiez Le Goff & Anne-Françoise Bonnot and T. Marlaud (AREVA), D. Pierron (AREVA), L. Forest (CEA), J.-P. Mathieu
More informationWATLOW A Trusted and Reliable Partner
Watlow Products and Technical Support Delivered Worldwide Watlow Watlow has grown in product capability, market through decades of building key relationships and developing world-class experience and global
More information