EU Contribution to ITER Fuel Cycle
|
|
|
- May Brooks
- 5 years ago
- Views:
Transcription
1 EU Contribution to ITER Fuel Cycle Update on technical and status Alain Teissier Project Manager Cryoplant and Fuel Cycle Fusion for Energy 1 Outline For each type of Fuel Cycle components to be procured by F4E, we will present an overview of: The equipment. The duties to be fulfilled by the equipment. The plan. The experience required for supplying the equipment. The schedule. EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF
2 Fuel Cycle components to be procured by F4E: Vacuum Pumping. Tritium Plant. Radiological and Environmental Monitoring Systems. Waste Management Systems. EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF Vacuum pumping Equipment: Cryopumps = vacuum pumps which trap gases and vapours on a cold surface. Cold valve boxes and cryolines. Leak detection and localisation components. Duties: To provide the ITER tokamak with clean, ultra high vacuum at large pumping speed. To distribute helium to and from the cryopumps. To detect and locate leaks. Procurement plan: Contracts for design. Contracts for manufacturing (including final design as regard the cold valve boxes and cryolines). Experience required: For design: vacuum, cryogenics. For manufacturing: welding and machining, helium leak detection, metrology, cleanliness, coating, pressure equipment. EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF
3 Vacuum pumping Cryopumps Cryopump design Timescale Call to be launched in: (done) Pre production cryopump MITICA cryopump End 2013 Torus and cryostat cryopumps (x 8) Neutral Beam cryopumps (X 4) Mid baffles support structure cryo feed ITER neutral beam cryopump For evacuation of beam line vessel Very low pressure (10 7 Pa) EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF Vacuum pumping Cold valve boxes, cryolines, leak detection and localization components Cold valve boxes and cryolines preliminary design Warm regeneration lines (for cryopump regeneration) Cold valve boxes (X12) and auxiliaries Leak detection and localization Timescale Call to be launched in: Mid 2013 Early m 1.8 m 1.8 m Cold valve box EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF
4 Tritium plant Tokamak building Assembly hall Power supply Cryoplant Diagnostics Tritium plant building Hot cells Radwaste Hot basin & cooling towers EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF Tritium plant Equipment: Water detritiation system. Isotope separation system. Medium low tritiated water holding tanks (20 m3) Emergency tanks (100 m3) Feeding tanks LPCE columns Duties: To detritiate water. To produce pure deuterium as well as 90% tritium/10% deuterium mixture. Procurement plan: Contracts for conceptual design. Contracts for preliminary design. Contracts for final design and manufacturing. High level tritiated water holding Tanks (5 m3) Electrolyser units Water detritiation system Competences required: Chemical component separation (cryogenic distillation, catalysts). Experience in handling of tritiated gases, large component manufacturing. EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF
5 LPCE columns Tritium plant Water detritiation system (WDS) 4500 Nm 3 /h air Detritiation of water (20 kg/h@10 Ci/kg) by CECE (Combined Electrolysis Catalytic Exchange) method: cracking water into hydrogen and oxygen, stripping the residual tritium from the hydrogen before its release. Environment via Detritiation System 20 kg/h demineralized water Moisture separation H 2 dilution Environment Flame arrester O 2 processing system 20 kg/h 10 Ci/kg Front-end processing system ISS Q 2 O Dryer unit Membrane permeator ISS L L M L H L Holding tanks Electrolyser system EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF Tritium plant Water detritiation system (WDS) WDS tanks Procurement Arrangement signed by IO and F4E in December WDS conceptual and preliminary designs WDS tanks (2 x 100 m3 and 4 x 20 m3) WDS Main Timescale Call to be launched in: April m3 WDS tanks (x 2) Stainless steel type 304L, ASME B&PV VIII (ASME III for seismic analysis), Not classified as pressure equipment. EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF
6 Tritium plant Isotope separation system (ISS) ISS conceptual design Timescale Call to be launched in: ISS preliminary design Mid 2015 ISS End 2016 EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF Radiological and Environmental Monitoring Systems Equipment: Radiological detectors and process systems. Personnel control and environmental monitoring systems. Duties: To monitor radiations and particles (room, process, personnel). To monitor environment. Procurement plan: Many components are off the shelf items but need to be adapted to ITER requirements. Procurement split into three phases: preliminary design; final design; manufacturing, on site installation and tests. Competences required: Sensors and detectors for nuclear use. Experience in radiological and environmental safety. System integration (electronics, software). EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF
7 Radiological and Environmental Monitoring Systems REMS preliminary equipment list HP laboratory Atomic Absorption Spectrophotometers (2) Smear test counter (3) Microwave digesters (2) Glove boxes (7) Gamma spectrometers (4) Liquid scintillation counters (5) Total gamma detectors (4) Alpha/beta counters (1) Laboratory Plant Control System Area Be Monitoring System (ABMS) Be Samplers (50) Process Control Tritium detectors HVAC/DS (201) Tritium detector port cell (10) Logic module 2/3 (67) Individual Monitoring System (IMS) Dosimeters Integrator [β/γ] (1600) Dosimeters Integrator [Neutron] (50) Electronic dosimeters (750) Dosimeters readers (10) Dosimeter Plant Control System Personal Be samplers (50) Personal Gas monitors (50) Portable X rays monitors (3) Be particulate in air samplers (5) Portable T in air samplers (2) Portable aqueous samplers (20) Portable Ra monitors (2) Portable gamma monitors (17) α/β particulate samplers (2) Portable β/γ surface cont. monitors (12) Portable neutron monitors (7) Whole body counters (2) Breathing air analyzer (2) Tools monitors (2) and Portal monitors (2) Friskers (35) and floor Monitors (2) Particulate samplers (25) Portable T samplers (18) Portable C 14 sampler (5) Mobile gamma monitors (30) Mobile gas monitors (4) Mobile β/γ monitors (25) Mobile T monitors (50) Contamination checking at fence (1) Dosimetry Plant Control System Area Radiological Monitoring System (ARMS) Gamma monitors (151) Neutron monitors (15) Tritium monitors (83) and gas monitors (7) Particulate monitors (7) HT/HTO discrimination samplers (60) Particulate samplers (43) C 14 sampler (1) ARMS Plant Control System Release Monitoring System (RMS) Gamma monitor (1) Tritium monitors (4) and gas monitors (4) Particulate samplers & monitors (4) HT/HTO discrimination samplers (2) Be particulate samplers (2) α/β particulate sampler (1) C 14 samplers (2) Flow rate meters (6) Environmental Monitoring System (EMS) Dosimeter Integrator (150) Be particulate samplers (8) NOx gas analyzers (5) Gamma monitors (9) HT/HTO discrimination samplers (11) C 14 samplers (1) Particulate samplers (8) EMS Plant Control System EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF Radiological and Environmental Monitoring Systems Area Radiological Monitoring System Distributed Architecture EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF
8 Radiological and Environmental Monitoring Systems REMS conceptual design REMS preliminary design REMS final design REMS Timescale Call to be launched in: Mid 2013 (task order from an existing framework contract) Mid 2014 (task order from an existing framework contract) 2016 EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF Waste Management Systems Equipment: Radioactive liquid treatment and storage systems. Solid waste characterization equipment, waste processing and storage. Duty: To process Type A Rad and conventional waste. Procurement plan: Mostly industrial items to be adapted to ITER requirements. Procurement split into three phases: preliminary design; final design; manufacturing, on site installation and tests. Competences required: radioactive and activated waste management. EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF
9 Waste Management Systems Type A WMS pre conceptual design EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF Waste Management Systems WMS conceptual design WMS preliminary design Timescale Call to be launched in: Mid 2014 (task order from an existing framework contract) WMS final design Mid 2016 WMS EU Contribution to ITER Fuel Cycle, Alain Teissier, IBF
10 Follow us on:
ITER Status & Opportunities. Meeting with CONFINDUSTRIA Piemonte Torino, November 16 th 2015 Benjamin Perier
ITER Status & Opportunities Meeting with CONFINDUSTRIA Piemonte Torino, November 16 th 2015 Benjamin Perier AGENDA Fusion ITER Fusion for Energy (F4E) Project status Business Opportunities what/how? F4E
Buildings Construction Procurement Strategy
Buildings Construction Procurement Strategy Update Q3 2018 Disclaimer: This presentation is given for information only and cannot be considered as binding Ref. F4E_D_2ABES6 v4.7 1 Table of Contents 1.
Buildings Construction Procurement Strategy
Buildings Construction Procurement Strategy Update August 2015 Disclaimer: This presentation is given for information only and cannot be considered as binding Ref. F4E_D_2NAKWC 1 Table of Contents 1. Overview
INFORMATION DAY. Fusion for Energy (F4E)
INFORMATION DAY 26th November 2013, Zagreb Fusion for Energy (F4E) Part 2 Status of the ITER Project and Achievements Jesus Izquierdo Technical Coordination and Integration 1 THE ITER PROJECT MAIN SYSTEMS
Safety Classification of Mechanical Components for Fusion Application
Safety Classification of Mechanical Components for Fusion Application 13 rd International Symposium on Fusion Nuclear Technology 25-29 September 2017, Kyoto, Japan Oral Session 1-2: Nuclear System Design
EU Contribution to ITER Remote Handling
EU Contribution to ITER Remote Handling Updates on technical and procurement status Carlo Damiani Project Manager Remote Handling Team Fusion for Energy 1 Outline Overview on ITER Remote Handling Situation
DRAFT DOCUMENT SUBJECT TO MODIFICATIONS. Foreseen Procedure. Estimated spending
TENDER DETAILS SUMMARY WP Ref. Division Name WP10/BA/03 Broader Approach Foreseen Procedure Estimated spending Magnets Strand qualification phase tests Negotiated < 250k Aim: quality control for NbTi strands
FUSION FOR ENERGY The European Joint Undertaking for ITER and the Development of Fusion Energy
FUSION FOR ENERGY The European Joint Undertaking for ITER and the Development of Fusion Energy THE GOVERNING BOARD F4E(12)-GB22-10b DECISION OF THE GOVERNING BOARD ENDORSING THE PRELIMINARY WORK PROGRAMME
ITER Organization. Françoise Flament. Head of Procurement Arrangements & Contracts Division. Journée ITER/CEA 01/12/2010. Page 1
ITER Organization Françoise Flament Head of Procurement Arrangements & Contracts Division Page 1 1. Overview of the IO Procurement System 2. Business Opportunities 3. IO Procurement Processes and Procedures
Technical Summary. Contract for Procurement of Piping and Fittings (IO/14/CFT/9560/ACS CP/1)
Technical Summary IO/14/CFT/9560/ACS CP/1 Version 2.0 dated 29/09/14 Technical Summary Contract for Procurement of Piping and Fittings (IO/14/CFT/9560/ACS CP/1) Control of modifications Version Section(s)
Buildings Construction Procurement Strategy
Buildings Construction Procurement Strategy Update January 2013 Disclaimer: This presentation is given for information only and cannot be considered as binding Ref. F4E_D_264U97 1 Agenda 1. Overview of
3ème RV Business du Nucléaire Civil en PACA. ITER Organization Future Call for Tenders
3ème RV Business du Nucléaire Civil en PACA ITER Organization Future Call for Tenders Disclaimer: The views and opinions expressed herein do not necessarily reflect those of the ITER Organization Outline
Specific technologies involved Near term opportunities for Industry Future opportunities for Industry (hints)
Neutral Beam System and Electron Cyclotron Power Supplies and Sources Tullio Bonicelli Project Team Manager NB and EC PS&S IBF13 21 22 March 2013, Toulon, France Objectives Scope of main future European
The ITER Neutral Beam Test Facility. Design Overview. European Tasks ref. TW3-THHN-IITF1 ( ) TW4-THHN-IITF2 ( ) Jean-Jacques Cordier
The ITER Neutral Beam Test Facility Design Overview European Tasks ref. TW3-THHN-IITF1 (2003-2004) TW4-THHN-IITF2 (2004-2005) Jean-Jacques Cordier on behalf of EU Associations involved in the study 4 th
Special features of ITER Cryogenic system
Special features of ITER Cryogenic system A. Girard*, JY Journeaux, JM Poncet*, and CEA cryogenic group CEA Grenoble* and Cadarache Outline 1. Tokamak operation from CEA Tore Supra experience 2. ITER:
Technical Summary. 1. Purpose
1. Purpose Technical Summary The purpose of this procurement is to establish a contract to provide mechanical and electrical plant installation works in the following areas on the ITER Site in Saint-Paul
Operation of a 2-Mg/Year Heavy-Water Detritiation Plant
Operation of a 2-Mg/Year Heavy-Water Detritiation Plant W. T. Shmayda, C. R. Shmayda, C. Waddington, and R. D. Gallagher University of Rochester Laboratory for Laser Energetics Tyne Engineering Nuclear
Background information for Procurement Procedure F4E-OPE-301 (TB04)
Background information for Procurement Procedure F4E-OPE-301 (TB04) HVAC (Heating, Venting, Air Conditioning), ELECTRICAL, I and C (Instrumentation & Control) Handling Equipment and Gas and Liquid Networks:
ITER ITA NEWSLETTER. No. 13, FEBRUARY 2004 INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, AUSTRIA ISSN
ITER ITA NEWSLETTER No. 13, FEBRUARY 2004 INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, AUSTRIA ISSN 1727 9852 COMMON MESSAGE FROM SECOND PREPARATORY MEETING FOR MINISTERIAL MEETING FOR ITER Delegations
Design Characteristics of the Cold Neutron Source in HANARO Process System and Architecture Design
Design Characteristics of the Cold Neutron Source in HANARO Process System and Architecture Design Sang Ik Wu, Young Ki Kim, Kye Hong Lee, Hark Rho Kim Korea Atomic Energy Research Institute (KAERI), Daejeon,
ITER Organization. Procurement Process Industrial Strategy Business Opportunities
ITER Organization Procurement Process Korean ITER Business Forum Seoul, 1-4 July 2014 IO/ADM/GEA/PCD Françoise Flament The views and opinions expressed herein do not necessarily reflect those of the ITER
Buildings Construction Procurement Strategy
Buildings Construction Procurement Strategy Update March 2012 Disclaimer: This presentation is given for information only and cannot be considered as binding Ref. F4E_D_24Y2K9 Agenda 1. Overview of the
Hot Cell Complex Building Engineering Contract (REVISED)
Hot Cell Complex Building Engineering Contract (REVISED) Call for Nomination It is important to note that participation in this tender process will NOT cause a conflict of interest (and hence exclusion)
ITER REMOTE HANDLING SYSTEM
ITER REMOTE HANDLING SYSTEM Alessandro Tesini ITER International Organization Remote Handling Section 1 Remote Handling A.Tesini Nice France 10-12 December 2007 Acropolis Congress Centre Contents 1. ITER
ITER R&D Needs, Challenges, and the Way Forward
ITER R&D Needs, Challenges, and the Way Forward Bernard Bigot Director General ITER Organization, Cadarache, France Fusion Power Co-ordinating Committee Mtg, IO Headquarters, 24 Jan 2018 1 Context of ITER
Mario Cavinato On behalf of Antennas and Plasma Engineering group
Mario Cavinato On behalf of Antennas and Plasma Engineering group 1 Ion Cyclotron Antenna Electron Cyclotron Upper launchers and Ex-Vessel waveguides Plasma Engineering 2 Ion Cyclotron Antenna: Component
Engineering Support in the Areas of Vacuum, Cryogenics and Instrumentation for ITER Magnet Feeders and Vacuum System. Technical Specification
CONTRACT TECHNICAL SPECIFICATION Engineering Support in the Areas of Vacuum, Cryogenics and Instrumentation for ITER Magnet Feeders and Vacuum System Technical Specification Page 1 of 6 Table of Contents
METHODOLOGY FOR ENSURING THE INTEGRATION OF ALARA INTO THE DESIGN OF
METHODOLOGY FOR ENSURING THE INTEGRATION OF ALARA INTO THE DESIGN OF THE AP1000 TM REACTOR Erik Slobe slobeed@westinghouse.com Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township,
Status of ITER Buildings construction and next procurement steps
Status of ITER Buildings construction and next procurement steps Laurent Schmieder Site, Buildings and Power Supplies Project Manager IBF/15 DIRECTORY IBF/15 March 25-27 March 25-27, 2015 Palais du Pharo
Safety in Cryogenics. Cryogen Handling Hazards. Bernd Petersen DESY MKS1 Quellen (u.a):
Safety in Cryogenics Cryogen Handling Hazards Quellen (u.a): Goran.Perinic@cern.ch Objectives: at the end of this lesson you should remember the following hazards cold burns embrittlement asphyxiation
TECHNICAL NOTE RELATED TO THE MARKET SURVEY OF THE PF COILS COLD TEST FACILITY SUPPLIER
Page 1 / 15 Ver. 1.1 TECHNICAL NOTE RELATED TO THE MARKET SURVEY OF THE PF COILS COLD TEST FACILITY SUPPLIER Abstract The experimental fusion reactor ITER will require the European supply of the Poloidal
Technical Summary. Purpose. ITER_D_RZ5S7J v2.1
Purpose Technical Summary The purpose of this project is to provide mechanical and electrical plant installation works in the following Buildings on the ITER Site in Saint-Paul Lez Durance, France: Building
Key Features and Progress of the KSTAR Tokamak Engineering
1 Key Features and Progress of the KSTAR Tokamak Engineering J. S. Bak, C. H. Choi, Y. K. Oh, Y. S. Kim, N. I. Her, K. H. Im, H. L. Yang, B. C. Kim, I. K. Yoo, J. W. Sa, H. K. Kim, M. Kwon, G. S. Lee,
ITER Remote Maintenance
ITER Remote Maintenance Overview on Remote Handling Procurement Van Hille Carine Van Uffelen Marco on behalf of the RH Project Team Liège SOFT 2012 Industry meeting 25 th September 2012 EU RH PP 23.03
High Temperature Blanket and Its Socio-Economic Issues. Satoshi Konishi Institute of Advanced Energy, Kyoto University
High Temperature Blanket and Its Socio-Economic Issues Satoshi Konishi Contents - Fast track and Development Strategy in Japan - Power plant design - Hydrogen production - Safety and environmental impact
NOTIFICATION ON SCHEDULE OF PRESCRIBED SUBSTANCES UNDER ATOMIC ENERGY ACT January 2006
NOTIFICATION ON SCHEDULE OF PRESCRIBED SUBSTANCES UNDER ATOMIC ENERGY ACT 1962 20 January 2006 Click here for hindi version THE SCHEDULE Category 0 : Nuclear materials, nuclear-related other materials,
Survey of technological development for the European Test Blanket Systems in ITER
Survey of technological development for the European Test Blanket Systems in ITER M. Ferrari and the F4E TBM & MD Project Team Monaco ITER International Fusion Energy Days (MIIFED) ITER Business Forum
Fusion: the fundamental principle
The ITER Project The ITER Project The ITER Project aims to demonstrate the scientific and technological feasibility of fusion power for peaceful purposes. Iter project is an international cooperation between
Membrane Technologies for Tritium Recovering in the Fusion Fuel Cycle
Membrane Technologies for Tritium Recovering in the Fusion Fuel Cycle S. Tosti 1), L. Bettinali 1), C. Rizzello 2), V. Violante 1) 1) Euratom-ENEA Fusion Association, C. R. ENEA Frascati, 00044 Frascati
ECE 541/ME 541 Microelectronic Fabrication Techniques
ECE 541/ME 541 Microelectronic Fabrication Techniques MW 4:00-5:15 pm Introduction to Vacuum Technology Zheng Yang ERF 3017, email: yangzhen@uic.edu ECE541/ME541 Microelectronic Fabrication Techniques
Integrated System Level Simulation and Analysis of DEMO with Apros. Sami Kiviluoto
Integrated System Level Simulation and Analysis of DEMO with Apros Sami Kiviluoto 3.11.2016 DEMO modelling project Fortum joined FinnFusion consortium in the fall 2015 EUROfusion WPPMI project (Plant Level
Preliminary Design of ITER Component Cooling Water System and Heat Rejection System
Preliminary Design of ITER Component Cooling Water System and Heat Rejection System A.G.A. Kumar 1, D.K. Gupta 1, N. Patel 1, G. Gohil 1, H. Patel 1, J. Dangi 1, L. Sharma 1, M. Jadhav 1, L. Teodoros 2,
Design Analysis for the development of the design of the ITER Hot Cell Complex (HHC)
IDM UID T78ULN VERSION CREATED ON / VERSION / STATUS 01 Sep 2016 / 1.0 / Approved EXTERNAL REFERENCE / VERSION Technical Specifications (In-Cash Procurement) Design Analysis for the development of the
ARIES Safety-Related Components and Nuclear Grade Requirements
ARIES Safety-Related Components and Nuclear Grade Requirements L. El-Guebaly, University of Wisconsin-Madison L. Cadwallader and B. Merrill Idaho National Laboratory Contributors: N. Taylor (ITER) and
Internal exposure at Cernavoda NPP. Vasile Simionov, Catalina Chitu,
Internal exposure at Cernavoda NPP Vasile Simionov, vsimionov@cne.ro, Catalina Chitu, cchitu@cne.ro CNE Cernavoda NPP, No. 2, Medgidiei Str. Cernavoda 905200, Romania 1.0 INTRODUCTION Work efficiency is
NOT EVERY HYBRID BECOMES A PRIUS: THE CASE AGAINST THE FUSION-FISSION HYBRID CONCEPT
NOT EVERY HYBRID BECOMES A PRIUS: THE CASE AGAINST THE FUSION-FISSION HYBRID CONCEPT IAP 2010 DON STEINER PROFESSOR EMERITUS,RPI JANUARY 22, 2010 IN 1997 TOYOTA INTRODUCED ITS HYBRID CAR CALLED THE PRIUS
Technical Summary for the Tokamak Assembly Works- A0
IDM UID S7YD73 VERSION CREATED ON / VERSION / STATUS 30 Jan 2017 / 1.3 / Approved EXTERNAL REFERENCE / VERSION Technical Specifications (In-Cash Procurement) Technical Summary for the Tokamak Assembly
Fusion for Energy The European Domestic Agency for ITER. F4E Contracts & Procurement Unit
Fusion for Energy The European Domestic Agency for ITER F4E Contracts & Procurement Unit Market Policy Group Agenda 1. Fusion Energy 2. ITER 3. Europe in ITER: F4E Fusion for Energy 4. F4E Contractual
Technical Specification - Hot Cell Complex - Mechanical Engineering
IDM UID TX82V9 VERSION CREATED ON / VERSION / STATUS 04 Nov 2016 / 1.0 / Signed EXTERNAL REFERENCE / VERSION Technical Specifications (In-Cash Procurement) Technical Specification - Hot Cell Complex -
Attachment 1. External Experts Areas of Expertise
Attachment 1 External Experts Areas of Expertise 1 - Complex civil constructions, nuclear buildings Secondary work Finishing Heating Ventilation and Air Conditioning Fluids Nuclear ventilation Cranes and
Call for Nomination. Vacuum Vessel Assembly Welding
Call for Nomination Vacuum Vessel Assembly Welding Purpose ITER will be the world's largest experimental facility to demonstrate the scientific and technical feasibility of fusion power. The Vacuum Vessel
ME RER First Coordination Meeting Warsaw, Poland June 2018
IAEA RER1020 Project To enhance and consolidate regional capability in on-line industrial process diagnosis, optimization and troubleshooting, using radiotracers and sealed source techniques Edited by
CRYOGENIC SOLVENT ABATEMENT (VOC s )
CRYOGENIC SOLVENT ABATEMENT (VOC s ) 1. Introduction The technology for removing volatile organic compounds (V.O.C.s) from gas has been developed to meet the emission limits, decreased during the last
Physics 100 Lecture 24. Fusion Energy and Fuel Cells April 30, 2018
1 Physics 100 Lecture 24 Fusion Energy and Fuel Cells April 30, 2018 2 Class quiz Chs 16-18: What is the key advantage of using biofuels? A. They are non-polluting. B. Burning them releases no CO 2 C.
AIR LIQUIDE AND ITER WHEN THE EXPERTS IN CRYOGENICS FUSE THEIR ENERGIES
AIR LIQUIDE AND WHEN THE EXPERTS IN FUSE THEIR ENERGIES , A UNIQUE PROJECT SEVEN INTERNATIONAL PARTNERS The magnitude of the scientific, technical and organizational challenge, plus the considerable resources
Status of Design and Research & Development for ITER Sector Sub-assembly Tools
1 ITR/P1-47 Status of Design and Research & Development for ITER Sector Sub-assembly Tools K.O. Nam 1), H.K. Park 1), D.J. Kim 1), H.J. Ahn 1), J.H. Lee 2), K.K. Kim 2), K. Im 3), R. Shaw 3) 1) National
Reactor Boiler and Auxiliaries - Course 133. The following terms are in common usage in the heavy water upgrading field: Heavy Water
133.62-1 Reactor Boiler and Auxiliaries - Course 133 UPGRADING RE~UIREME~TS A~D PROCESSES The following terms are in common usage in the heavy water upgrading field: Heavy Water Isotopic Purity - Upgrading
Technical Description of the Cryolinks
Technical Description of the Cryolinks Nikhef number: Item number: Date: 19/12/2012 Page: 1 of 10 47110-MT-00007 AA2830 Status: In Work Revision: A.6 Project: Gravitational Waves Virgo Cryogenic Link Department:
3.6 Site Layout and Buildings
3.6 Site Layout and Buildings 3.6.1 Site Layout 2 3.6.2 Buildings 2 3.6.3 Specific Design of the Radiologically Controlled Buildings 4 3.6.3.1 Radiation Shielding 4 3.6.3.2 Radioactive Contamination Confinement
CANDU Fundamentals. Table of Contents
Table of Contents 1 OBJECTIVES... 1 1.1 COURSE OVERVIEW... 1 1.2 ATOMIC STRUCTURE... 1 1.3 RADIOACTIVITY SPONTANEOUS NUCLEAR PROCESSES... 1 1.4 NUCLEAR STABILITY AND INSTABILITY... 2 1.5 ACTIVITY... 2
PRESENTATION OF NUCLEAR APPLICATIONS OF CONDENSATE TREATMENT
Via Pietro Nenni, 15-27058 VOGHERA ITALY Tel. +39 0383 3371 Fax +39 0383 369052 E-mail: info@idreco.com PRESENTATION OF NUCLEAR APPLICATIONS OF CONDENSATE TREATMENT 0. MAIN CONDENSATE TREATMENT 1. REACTOR
Demonstration Test Program for Long term Dry Storage of PWR Spent Fuel
Demonstration Test Program for Long term Dry Storage of PWR Spent Fuel 16 November 2010 K.Shigemune, The Kansai Electric Power Co., Inc. The Japan Atomic Power Company Kyushu Electric Power Co., Inc. Mitsubishi
Safety Issues in TBM Program
Idaho National Engineering and Environmental Laboratory Safety Issues in TBM Program Brad Merrill, Dave Petti 1 Hans-Werner Bartels 2 1 Fusion Safety Program 2 ITER IT, Safety Group APEX/TBM Meeting, UCLA,
Radiation Safety Training Session 2: Radiation Protection Systems and Guidelines
Radiation Safety Training Session 2: Radiation Protection Systems and Guidelines Reading Assignment: LLEINST 6610 Part II, pp. 1 9 Walter T. Shmayda Radiation Safety Officer Laboratory for Laser Energetics
Technical Specifications (In-Cash Procurement)
IDM UID XLVFDB VERSION CREATED ON / VERSION / STATUS 03 Dec 2018 / 1.2 / Approved EXTERNAL REFERENCE / VERSION Technical Specifications (In-Cash Procurement) Technical specification - Mechanical design
El Séptimo Programa Marco de I+D de la Unión Europea Cómo tener éxito en las convocatorias 2013
El Séptimo Programa Marco de I+D de la Unión Europea Cómo tener éxito en las convocatorias 2013 Activity: Research and Development Title: Empresarios Agrupados: an innovative company Experience in the
Nuclear Products, Materials and Services
2012 Nuclear Canada Yearbook Nuclear Products, Materials and Services Canadian Nuclear Society 2012 Annual Industry Review and Buyer s Guide 61 62 50 Years of Nuclear Electricity in Canada Nuclear Products,
ITER Assembly Opportunities
ITER Assembly Opportunities Assembly Workshop Robert Shaw ITER Organization 1 Assembly Workshop Robert Shaw Nice France 10-12 December 2007 Acropolis Congress Centre Contents Overview of the ITER Machine
ITER Fuelling System Design and Challenges Gas and Pellet Injection and Disruption Mitigation
ITER Fuelling System Design and Challenges Gas and Pellet Injection and Disruption Mitigation ITR/P1-28 S. Maruyama 1, Y. Yang 1, R.A. Pitts 1, M. Sugihara 1, S. Putvinski 1, S. Carpentier-Chouchana 1,
The Heat Rejection System of the ITER Reactor
The Heat Rejection System of the ITER Reactor G. Dell Orco, W. Curd, D. Gupta, L. Fan, K.P. Chang, I. Kuehn, A. Kumar* International Thermonuclear Experimental Reactor Organization (ITER-IO) 13108 Saint
Radiation Safety Training Instructions
Radiation Safety Training Instructions According to state law and its interpretation by the campus office of Environmental Health and Safety, it is required that all faculty, TAs, and students in Physics
Calculation of Water Activity in Point 7
Calculation of Water Activity in Point 7 SC/RP, M. Brugger, S. Roesler joachim.vollaire@cern.ch Calculation of Water Activity in Point 7 Production of radioactive nuclei in water Production on Oxygen atom
6.0 ENGINEERED SAFETY FEATURES
Engineered Safety Features Materials 6.0 ENGINEERED SAFETY FEATURES This chapter of the U.S. EPR Final Safety Analysis Report (FSAR) is incorporated by reference with supplements as identified in the following
The Tokamak Concept. Magnetic confinement. The Tokamak concept
Major radius Minor radius The Tokamak Concept ITER is based on the tokamak concept. A tokamak is a device able to produce and confine a large volume of high temperature plasma -a mixture of electrons and
ITER TOKAMAK VACUUM VESSEL THERMAL SHIELD ADDITIONAL NEUTRAL SHIELDING
Route de Vinon-sur-Verdon - CS 90 046-13067 St Paul Lez Durance Cedex - France ITER TOKAMAK VACUUM VESSEL THERMAL SHIELD ADDITIONAL NEUTRAL SHIELDING CALL FOR NOMINATION Ref. IO/CFN/14/11176/PMT SUMMARY
Experimental 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
On-Line Diagnostics Techniques in the Oil, Gas, and Chemical Industry
On-Line Diagnostics Techniques in the Oil, Gas, and Chemical Industry 1. INTRODUCTION Lee Robins, Business Development Manager, Tracerco lee.robins@matthey.com Unfortunately, the vessels and pipelines
Safety Aspects of the RA-6 Spent Fuel Shipment to the USA
Safety Aspects of the RA-6 Spent Fuel Shipment to the USA Oscar Novara, Guillermo Facchini, Carlos Fernández Comisión Nacional de Energía Atómica, Av del Libertador 8250, (1429), Buenos Aires, Argentina
Safety and Environment Studies for a European DEMO Power Plant. Neill Taylor, SAE Project Leader
Safety and Environment Studies for a European DEMO Power Plant Neill Taylor, SAE Project Leader Outline Background Safety and environmental potential of fusion Aims and objectives of Safety and Environment
Conceptual system design of non-nuclear grade IS process to be coupled with the HTTR
Conceptual system design of non-nuclear grade IS process to be coupled with the HTTR N. Sakaba, H. Sato, H. Ohashi, T. Nishihara, K. Kunitomi Monday, 16 April 2007 IAEA-CN-152, Oarai, Japan Japan Atomic
Status of the HCLL and HCPB Test Blanket System instrumentation development
Status of the HCLL and HCPB Test Blanket System instrumentation development Pattrick Calderoni The European Joint Undertaking for ITER and the Development of Fusion Energy ('Fusion for Energy' ) ITER Department
Recent developments on quality assurance of fuel cell hydrogen
Recent developments on quality assurance of fuel cell hydrogen Arul Murugan, Thomas Bacquart, Paul Brewer Gas Metrology Group NPL Cutting Edge Research for Gas Metrology, CCQM-GAWG (13 Oct 2016) Project
Posting Radiological Hazards RP RP Approved Rev: 11/29/17
Posting Radiological Hazards RP 02.04 RP 03.04 Approved Rev: 11/29/17 Standardized Task Evaluation Program The Standardized Task Evaluation (STE) program promotes a work-ready workforce through the standardization
Fusion Reactions 3/18/2016. Exam #2 Results. Nuclear Fusion (not Fission) Clicker Question. U n Te Zr n
Clicker Question What do you think? A) We should increase our nuclear fission energy facilities. B) We should continue to run only the facilities we currently have. C) We should shut down all existing
Pressurized Water Reactors
Pressurized Water Reactors Illustrations and information from http://en.wikipedia.org/wiki/pressurize d_water_reactor The Ikata Nuclear Power Plant is located on Shikoku island at Ikata-cho. Heavy vs.
ITER Vacuum Vessel Status and Procurement
ITER Vacuum Vessel Status and Procurement IBF, Nice 11 December 2007 Presented by K. Ioki Tokamak Department, ITER Organization 1 VV design Design Review Activities VV Procurement Contents Main Vessel
COLD 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
Design Progress and Analysis for ITER Thermal Shield
1 IT/P7-21 Design Progress and Analysis for ITER Thermal Shield W. Chung 1), K. W. Nam 1), C. H. Noh 1), B. C. Kim 1), J. W. Sa 1), Y. Utin 2), K. Ioki 2), N. I. Her 2), J. Yu 2), H. J. Ahn 1), K. J. Jung
Radioactive Materials from U.S. Nuclear Plants
Routine Releases of Radioactive Materials from U.S. Nuclear Plants Dave Lochbaum Union of Concerned Scientists August 2014 Revision i 1 1 The idea for this material came during a November 2013 workshop
Achievements of the Water Cooled Solid Breeder Test Blanket Module of Japan to the Milestones for Installation in ITER
1 Topic: FT/P2-6 Achievements of the Water Cooled Solid Breeder Test Blanket Module of Japan to the Milestones for Installation in ITER Daigo Tsuru, Hisashi Tanigawa, Takanori Hirose, Kensuke Mohri, Yohji
ITER Remote Handling: Overview and Technical Requirements
ITER Remote Handling: Overview and Technical Requirements TESINI Alessandro Remote Handling Section, ITER 22 Sep 2009 Alessandro.TESINI@iter.org Page 1 Outlines ITER Remote Handling Strategy ITER RH Operation
TRITIUM RELATED STUDIES WITHIN THE JET FUSION TECHNOLOGY WORK PROGRAMME
TRITIUM RELATED STUDIES WITHIN THE JET FUSION TECHNOLOGY WORK PROGRAMME S. Rosanvallon a, N. Bekris b, J. Braet c, P. Coad d, G. Counsell d, I. Cristescu b, C. Grisolia e, F. Le Guern a, G. Ionita f, J.
Nuclear Energy Revision Sheet
Nuclear Energy Revision Sheet Question I Identify the NPP parts by writing the number of the correct power plant part in the blank. Select your answers from the list provided below. 1 Reactor 2 Steam generator
FUSION FOR ENERGY The European Joint Undertaking for ITER and the Development of Fusion Energy
FUSION FOR ENERGY The European Joint Undertaking for ITER and the Development of Fusion Energy THE GOVERNING BOARD DECISION OF THE GOVERNING BOARD ADOPTING WORK PROGRAMME 03 OF THE EUROPEAN JOINT UNDERTAKING
Recruitment Field for Engineer
1 (1)Theme Fabrication, Assembly and Technology Development of Tokamak Components for the Satellite Tokamak JT-60SA The Satellite Tokamak Project (JT-60SA) is one of Broader Approach Programme implemented
Performances of Helium, Neon and Argon Glow Discharges for Reduction of Fuel Hydrogen Retention in Tungsten, Stainless Steel and Graphite
1 FTP/P7-10 Performances of Helium, Neon and Argon Glow Discharges for Reduction of Fuel Hydrogen Retention in Tungsten, Stainless Steel and Graphite T. Hino 1), Y. Yamauchi1), Y. Kimura1), A. Matsumoto1),
LOCATION. Three Mile Island, in the Susquehanna River, Londonderry Township, Dauphin County, about 10 miles south of Harrisburg, Pennsylvania.
LOCATION Three Mile Island, in the Susquehanna River, Londonderry Township, Dauphin County, about 10 miles south of Harrisburg, Pennsylvania. FACILITIES TMI Nuclear Unit 1, with a capacity of about 800
TABLE OF CONTENTS. 1.0 INTRODUCTION Page SCOPE Page REFERENCES Page REQUIREMENTS Page QUALITY ASSURANCE Page 8
TABLE OF CONTENTS 1.0 INTRODUCTION Page 3 2.0 SCOPE Page 3 3.0 REFERENCES Page 4 4.0 REQUIREMENTS Page 5 5.0 QUALITY ASSURANCE Page 8 6.0 SUBMITTALS Page 9 7.0 PREPARATION FOR SHIPMENT Page 10 Page 2 of
RADIOACTIVE WASTE MANAGEMENT AT CERNAVODA NPP AFTER 5 YEARS OF EXPERIENCE
International Conference Nuclear Energy for New Europe 2002 Kranjska Gora, Slovenia, September 9-12, 2002 www.drustvo-js.si/gora2002 RADIOACTIVE WASTE MANAGEMENT AT CERNAVODA NPP AFTER 5 YEARS OF EXPERIENCE
D&D OF A PU EXTRACTION FACILITY IN VNIINM
ABSTRACT D&D OF A PU EXTRACTION FACILITY IN VNIINM S.V.Mikheikin, S.L.Khrabrov, A.Yu.Smirnov, L.V.Pronina, P.P.Poluectov, V.F.Derzhavin, A.Ya.Chilikin (VNIINM) V.D.Akhunov (Minatom) Old Pu extraction facility