DCLL TBM Cost. Applying Module 18 Logic. August 10-12, M. Ulrickson Presented at US TBM Meeting at Idaho National Laboratory
|
|
- Joseph Bradford
- 6 years ago
- Views:
Transcription
1 DCLL TBM Cost Applying Module 18 Logic August 10-12, 2005 M. Ulrickson Presented at US TBM Meeting at Idaho National Laboratory Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy s National Nuclear Security Administration under contract DE-AC04-94AL85000.
2 Outline Costs Determined From Divertor EDA TBM Differences US ITER Cost Contingency Methodology My Estimate The WBS Structure for Mod 18 Open Issues Summary MAU 2 5/20/2003
3 Costs Determined From Divertor EDA A complete cost estimate was done for the ITER divertor (EDA) using fabrication techniques resulting from extensive R&D and testing. The cost estimate was done bottoms up by an Industry team and was very detailed. The divertor PFCs were actively cooled (CFC or W on Cu alloy on 316 LN SS) The cost of an actively cooled PFC per unit area is a good way to extrapolate cost. The cost was $300K/m 2 (escalated from 1996) MAU 3 5/20/2003
4 TBM Differences The TBM has a more complex cooling path. The TBM is He gas cooled. The TM has tighter radius bends on the plasma facing surface. There is no experience joining Be to Ferritic Steel Fabrication experience with Ferritic steel is limited My judgment is that the TBM will be X3 more expensive than the typical ITER PFC per unit area. MAU 4 5/20/2003
5 US ITER Cost Contingency Methodology The contingency to be placed on a cost estimate depends on the maturity of the design and R&D and an assessment of the project risks. Three factors are to be considered Technical risk based on the current state and level of design Cost risk based on estimating methodology Schedule risk based on the criticality to the overall project schedule The risk factors were weighted by the level of uncertainty and summed to get the contingency MAU 5 5/20/2003
6 MAU 6 5/20/2003 Technical Risk Existing Design and off the shelf hardware Minor modifications to an existing design Technical Risk Factors Risk Factor Extensive modification 3 New design, not exotic 4 New design slight difference 6 New design some R&D 8 New design advance SOA 10 New design way beyond SOA
7 Cost Risk Factors MAU 7 5/20/2003 Cost Risk Factor Off the shelf or catalog item 1 Vendor quote from draw gs 2 Vendor Quote from sketches 3 In-house estimate (exper.) 4 In-house est. (min-exper., sim. cap.) In-house est. (min. exper., no cap.) Top down (similar prog.) 10 Engineering Judgment
8 Schedule Risk Factors Schedule Risk Factor No schedule impact on any other subsystem 2 Delays completion of noncritical path subsystem 4 Delays completion of critical path subsystem 8 MAU 8 5/20/2003
9 Weighting Factors Area Condition Weight Technical Cost Design or Manufact. issues Design and Manufact. issues Material or labor uncertainties Material and labor uncertainties Schedule All MAU 9 5/20/2003
10 TBM Application Technical = 15(4); Cost = 15 (2); Schedule = 4 (1) Contingency is or 94% If the TBM is essential to meet the ITER mission and it must be installed by start of plasma operations, the schedule contingency doubles. This means that the contingency required is equal to the cost estimate! MAU 10 5/20/2003
11 My Estimate MAU 11 5/20/2003 Component Cost Estimate ($K) PFC 1500 Structure 800 SiC FCI? Auxiliary Systems 9300 He Loop 7500 PbLi loop 1800 T system? R&D (join, Be, mockups) 8200 Total ? For 10 cm frame thickness!
12 The WBS Structure for Mod 18 First Wall Administration R&D Be to Cu Joining Cu to 316 SS joining Prototype Testing Engineering Design (CDR, PDR, FDR) Title III Fabrication/procurement Spares MAU 12 5/20/2003
13 The WBS Structure for Mod 18 Shield Administration R&D Weld Development Casting Development Prototype Testing Engineering Design Title III Fabrication Assembly of FW to Shield Spares MAU 13 5/20/2003
14 Open Issues SiC flow channel inserts are complete unknowns (no R&D yet). The alternate insulator coatings are in early R&D stages and not proven with PbLi Fabrication of such complex Ferritic Steel structures is unknown. (joining, surface roughening for h c, load capacity of joints, etc.) Be to Ferritic joining is unknown (beryllide formation) QA/QC methods are unknown Size of auxiliary systems is uncertain (EM pump, He system) MAU 14 5/20/2003
15 Summary Some estimate of the cost of the DCLL TBM can be made using previous experience with PFCs for ITER. There are several key issues that require immediate R&D if the TBM must be installed on day 1 The recommended cost contingency is % of the estimated cost. The likelihood of occurrence of problems and consequence of an occurrence place the TBM in the high risk category. MAU 15 5/20/2003
Status Report and Documentation of DCLL Design
Status Report and Documentation of DCLL Design He primary and secondary loops footprint at TCWS DCLL design evolution DCLL, DEMO inboard routing assessment Documentation of DCLL design Clement Wong, Dick
More informationOverview of ARIES ACT-1 Study
Overview of ARIES ACT-1 Study Farrokh Najmabadi Professor of Electrical & Computer Engineering Director, Center for Energy Research UC San Diego and the ARIES Team Japan-US Workshop on Fusion Power Plants
More informationOverview and Meeting Objectives US ITER-TBM Meeting
Overview and Meeting Objectives US ITER-TBM Meeting Mohamed Abdou August 10-12, 2005 at INEL Purpose of the Meeting: To initiate the next phase (Phase 2) of US ITER-TBM activities - Definition of Tasks
More informationHCCB TBM Design and Fabrication Plan and Cost Estimate
HCCB TBM Design and Fabrication Plan and Cost Estimate From Cost Guideline Planning will be for the US Reference Scenarios: DCLL TBM with PbLi exit temperature of 470ºC and a series of TBM that occupy
More informationProgress on US Helium-Cooled Ceramic Breeder (HCCB) ITER TBM
Progress on US Helium-Cooled Ceramic Breeder (HCCB) ITER TBM A. Ying 1, M. Abdou 1, P. Calderoni 1, Y. Kaoth 2, R. Kurtz 3, S. Reyes 4, S. Sharafat 1, T. Tanaka 5, S. Willms 6, M. Youssef 1, S. Zinkle
More informationAn overview of dual coolant Pb 17Li breeder first wall and blanket concept development for the US ITER-TBM design
Fusion Engineering and Design 81 (2006) 461 467 An overview of dual coolant Pb 17Li breeder first wall and blanket concept development for the US ITER-TBM design C.P.C. Wong a,, S. Malang b,m.sawan c,
More informationAN OVERVIEW OF DUAL COOLANT Pb-17Li BREEDER FIRST WALL AND BLANKET CONCEPT DEVELOPMENT FOR THE US ITER-TBM DESIGN
GA A24985 AN OVERVIEW OF DUAL COOLANT Pb-17Li BREEDER FIRST WALL AND BLANKET CONCEPT by C.P.C. WONG, S. MALANG, M. SAWAN, M. DAGHER, S. SMOLENTSEV, B. MERRILL, M. YOUSSEF, S. REYES, D.K. SZE, N.B. MORLEY,
More informationFusion R&D Strategy from A Technology Viewpoint
Fusion R&D Strategy from A Technology Viewpoint Mohamed A. Abdou UCLA Presented at ISFNT-4, Tokyo, Japan 7 April, 1997 The Region Immediately Surrounding the Plasma Divertor / First Wall / Blanket /Vacuum
More informationRequirements for FNSF and DEMO
FNST Meeting 2-4 August 2010, UCLA A Historical Perspective on Test Stands for R&D in PFC/PMI and their role in addressing Requirements for FNSF and DEMO Richard Nygren and Matthew Baldwin Sandia is a
More informationARIES Issues and R&D Needs Technology Readiness for Fusion Energy
page 1 of 16 ARIES Issues and R&D Needs Technology Readiness for Fusion Energy M. S. Tillack ARIES Project Meeting 28 May 2008 page 2 of 16 The goal of the TWG s is to translate advisory committee recommendations
More informationProceedings. ExHFT June - 03 July 2009, Krakow, Poland. 7th World Conference on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics
i ExHFT-7 7th World Conference on Experimental Heat Transfer, Fluid Mechanics and Thermodynamics 28 June - 03 July 2009, Krakow, Poland Proceedings Editors: J.S. Szmyd, J. Spałek, T.A. Kowalewski v All
More informationFusion Nuclear Science & Technology. PFC Concepts and R&D towards DEMO Divertor Technology
Fusion Nuclear Science & Technology PFC Concepts and R&D towards DEMO Divertor Technology D.L. Youchison & R.E. Nygren Sandia National Laboratories A.R. Raffray Univ. of California San Diego Los Angeles,
More informationHCCB Engineering, Fabrication and Procurement, Ancillary Equipment, Interface and System Integration
HCCB Engineering, Fabrication and Procurement, Ancillary Equipment, Interface and System Integration WBS 1.8.2.1.3 Engineering 1.8.2.1.4 Fabrication/Procurement 1.8.2.2 Ancillary Equipment Prepared by
More informationUS ITER TEST BLANKET MODULE (TBM) PROGRAM VOLUME I: TECHNICAL PLAN AND COST ESTIMATE SUMMARY
REPORT NO. UCLA-FNT-216 US ITER TEST BLANKET MODULE (TBM) PROGRAM VOLUME I: TECHNICAL PLAN AND COST ESTIMATE SUMMARY BY: M.A. ABDOU, N.B. MORLEY, A.Y. YING, C.P.C WONG, T. MANN, S. TOURVILLE AND THE US
More informationEU considerations on Design and Qualification of Plasma Facing Components for ITER
EU considerations on Design and Qualification of Plasma Facing Components for ITER Patrick Lorenzetto, F4E Barcelona with inputs from B. Riccardi (F4E), V. Barabash and M. Merola (ITER IO) on Readiness
More informationAnalysis of Accident Scenarios of a Water-Cooled Tokamak DEMO
1 SEE/P5-1 Analysis of Accident Scenarios of a Water-Cooled Tokamak DEMO M. Nakamura 1, K. Ibano 2, K. Tobita 1, Y. Someya 1, H. Tanigawa 3, W. Gulden 4 and Y. Ogawa 5 1 Japan Atomic Energy Agency, Rokkasho,
More information2009 PFC Meeting. Two-phase CFD Analysis of ITER FW Hypervapotrons
2009 PFC Meeting Two-phase CFD Analysis of ITER FW Hypervapotrons D.L. Youchison, M.A. Ulrickson, J.H. Bullock Sandia National Laboratories Boston, MA July 9, 2009 Sandia is a multiprogram laboratory operated
More informationConcept of power core components of the SlimCS fusion DEMO reactor
Concept of power core components of the SlimCS fusion DEMO reactor K. Tobita, H. Utoh, Y. Someya, H. Takase, N. Asakura, C. Liu and the DEMO Design Team Japan Atomic Energy Agency, Naka, Ibaraki-ken, 311-0193
More informationPerspective on FNST Pathway. With major input from many experts. FNST/PFC/Materials/FNSF Meeting, UCLA, August 2 6, 2010
PriorFNST Studies and Perspective on FNST Pathway Mohamed Abdou With major input from many experts and colleagues over many years FNST/PFC/Materials/FNSF Meeting, UCLA, August 2 6, 2010 Fusion Nuclear
More informationAnnular Core Research Reactor Pneumatic Transfer System Design
Annular Core Research Reactor Pneumatic Transfer System Design September 21, 2010 Tri Q. Trinh*, Ed Rombach + *Sandia National Laboratories, NM Albuquerque, NM 87185-1142 + Automation Concepts Inc. Sandia
More informationA Brief Recount on Test Blankets (DEMO relevant blankets)
A Brief Recount on Test Blankets (DEMO relevant blankets) Clement Wong Neil Morley Alice Ying Sergey Smolentsev Mohamed Abdou Mohamed Sawan Rick Kurtz Dai-Kai Sze Siegfried Malang General Atomics UCLA
More informationDCLL Blanket for ARIES-AT: Major Changes to Radial Build and Design Implications
DCLL Blanket for ARIES-AT: Major Changes to Radial Build and Design Implications L. El-Guebaly Fusion Technology Institute UW - Madison ARIES-Pathways Project Meeting December 12-13, 2007 Georgia Tech
More informationCurrent Status of Chinese Solid Tritium Breeder TBM. Improved Design and Analyses of CN HCCB TBM
1234 25th IAEA FUSION ENERGY CONFERENCE FIP/3-5Ra+FIP/3-5Rb PIP/3-5Ra + FIP/3-5Rb Current Status of Chinese Solid Tritium Breeder TBM Improved Design and Analyses of CN HCCB TBM K.M. Feng 1 *, C.H. Pan
More informationARIES: Fusion Power Core and Power Cycle Engineering
ARIES: Fusion Power Core and Power Cycle Engineering The ARIES Team Presented by A. René Raffray ARIES Peer Review Meeting University of California, San Diego ARIES: Fusion Power Core and Power Cycle Engineering/ARR
More informationThe ITER Blanket System Design Challenge
The ITER Blanket System Design Challenge Presented by A. René Raffray Blanket Section Leader; Blanket Integrated Product Team Leader ITER Organization, Cadarache, France With contributions from B. Calcagno
More informationITER-FEAT Vacuum Vessel and Blanket Design Features and Implications for the R&D Programme
ITER-FEAT Vacuum Vessel and Blanket Design Features and Implications for the R&D Programme K. Ioki 1), W. Daenner 2), K. Koizumi 3), V.Krylov 4), A. Cardella 1), F. Elio 1), M. Onozuka 1), ITER Joint Central
More informationGA A22446 DESIGN, FABRICATION AND TESTING OF HELIUM-COOLED VANADIUM MODULE FOR FUSION APPLICATIONS
GA A22446 DESIGN, FABRICATION AND TESTING OF HELIUM-COOLED VANADIUM MODULE FOR FUSION APPLICATIONS by C.B. BAXI, E. CHIN, B. LAYCOCK, W.R. JOHNSON, R.J. JUNGE, E.E. REIS, and J.P. SMITH OCTOBER 1996 GA
More informationCURRENT DESIGN STATUS OF THE EU SOLID BREEDER TEST BLANKET MODULE
CURRENT DESIGN STATUS OF THE EU SOLID BREEDER TEST BLANKET MODULE L.V. Boccaccini, R. Meyder, H. Neuberger and the HCPB Design Team CBBI-13, Santa Barbara, 30th Nov. 2nd Dec., 2005 L.V. Boccaccini slide
More informationCOMPARISON OF STEADY-STATE AND PULSED-PLASMA TOKAMAK POWER PLANTS
COMPARISON OF STEADY-STATE AND PULSED-PLASMA TOKAMAK POWER PLANTS F. Najmabadi, University of California, San Diego and The ARIES Team IEA Workshop on Technological Aspects of Steady State Devices Max-Planck-Institut
More informationOVERVIEW OF FUSION BLANKET R&D IN THE US OVER THE LAST DECADE
OVERVIEW OF FUSION BLANKET R&D IN THE US OVER THE LAST DECADE M. A. ABDOU *, N. B. MORLEY, A. Y. YING, S. SMOLENTSEV and P. CALDERONI Mechanical & Aerospace Engineering Department, 44-114 Engineering IV,
More informationARIES-ACT-DCLL NWL Distribution and Revised Radial Build
ARIES-ACT-DCLL NWL Distribution and Revised Radial Build L. El-Guebaly and A. Jaber Fusion Technology Institute University of Wisconsin-Madison http://fti.neep.wisc.edu/uwneutronicscenterofexcellence Contributors:
More informationHe-cooled Divertor Development in the EU: The Helium Jet cooled Divertor HEMJ
He-cooled Divertor Development in the EU: The Helium Jet cooled Divertor HEMJ Presented by Thomas Ihli * Contributors: Divertor Group at, Germany and Efremov Institute, Russia ARIES Meeting General Atomics,
More informationIssues and R&D needs for commercial fusion energy An interim report of the ARIES technical working groups
University of California, San Diego UCSD-CER-08-01 Issues and R&D needs for commercial fusion energy An interim report of the ARIES technical working groups M. S. Tillack, D. Steiner, L. M. Waganer, S.
More informationOVERVIEW OF THE ARIES AND PULSAR STUDIES
OVERVIEW OF THE ARIES AND PULSAR STUDIES F. Najmabadi, R. W. Conn, University of California, San Diego and The ARIES Team ISFNT-3 University of California, Los Angeles June 27 July 1, 1994 ARIES Is a Community-Wide
More informationSilicon Carbide Tritium Permeation Barrier for Steel Structural Components
Silicon Carbide Tritium Permeation Barrier for Steel Structural Components Phase II SBIR Program Principle Investigator: Matt Wright Deuterium Permeation Studies: Sandia National Laboratories California
More informationObservatory Control System Project Management
Project Documentation Document PMCS-0020 Revision A Observatory Control System Project Management Bret Goodrich Software September 1, 2015 Advanced Technology Solar Telescope 950 N. Cherry Avenue Tucson,
More informationR&D required to place a test module on FNF (how does it compare to ITER TBM?) R&D required for base blanket
Testing Strategy, Implications for R&D and Design What are the preferred blankets options for testing on FNF and what are the implications for R&D? Comparison of strategies for testing space allocation
More informationMargins and Contingency Module Exploration Systems Engineering, version 1.0
Margins and Contingency Module Exploration Systems Engineering, version 1.0 Exploration Systems Engineering: Margins Module Module Purpose: Margins and Contingency Describe the need for and use of resource
More informationSafety 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,
More information4 Fusion Reactor and Fusion Reactor Materials
4 Fusion Reactor and Fusion Reactor Materials 4.1 Overview of research activities in Fusion Reactor and Materials Division Fusion Reactor Materials Division Abstract: Big progresses were made on each research
More informationDevelopment and Application of System Analysis Program for Parameters Optimization and Economic Assessment of Fusion Reactor (SYSCODE)
Development and Application of System Analysis Program for Parameters Optimization and Economic Assessment of Fusion Reactor (SYSCODE) Presented By Dehong Chen Contributed by FDS Team Key Laboratory of
More informationAssessment and comparison of pulsed and steady-state tokamak power plants
Assessment and comparison of pulsed and steady-state tokamak power plants Farrokh Najmabadi UC San Diego 21 st International Toki Conference, 28 Novemeber-1 December 2011 Toki, Japan Choice between steady-state
More informationLithium and Liquid Metal Studies at PPPL
Lithium and Liquid Metal Studies at PPPL LTX R. Maingi, M. Jaworski, R. Kaita, R. Majeski, J. Menard, M. Ono PPPL High Power Devices NSTX-U Surface Analysis EAST Test stands IAEA TM on Divertor Concepts
More informationARIES 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
More informationFPA-611: Development of simulation tools for the exploitation of the HCLL and HCPB TBM System operation in ITER. Technical scope
FPA-611: Development of simulation tools for the exploitation of the HCLL and HCPB TBM System operation in ITER Technical scope 1 OUTLINE 1 Introduction 2 4 3 Technical areas of interest Development strategy
More informationProgress on Design and R&D of CN Solid Breeder TBM
FTP/3-5Ra Progress on Design and R&D of CN Solid Breeder TBM K.M. Feng, G.S. Zhang, T.Y. Luo, Z. Zhao, Y.J. Chen, X.F. Ye, G. Hu, P.H. Wang. T. Yuan, Y.J. Feng, B. Xiang, L. Zhang, Q.J. Wang, Q.X. Cao,
More informationTechnical Specifications (In-Cash Procurement)
IDM UID V5MEWY VERSION CREATED ON / VERSION / STATUS 21 Jul 2017 / 1.1 / Approved EXTERNAL REFERENCE / VERSION Technical Specifications (In-Cash Procurement) Call for Nomination: Summary of the Technical
More informationRadwaste Management Issues. Radwaste Management Issues. L. El-Guebaly and L. Cadwallader. University of Wisconsin-Madison Idaho National Laboratory
Radwaste Management Issues Radwaste Management Issues L. El-Guebaly and L. Cadwallader University of Wisconsin-Madison Idaho National Laboratory ARIES-TNS Project Meeting Idaho Falls, Idaho September 6-7,
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 informationStrategy of WCCB-TBM Testing in ITER
Third IAEA DEMO Programme Workshop 13 May 2015 Hefei, China Strategy of WCCB-TBM Testing in ITER JAEA Blanket technology group Hisashi Tanigawa, T. Hirose, Y. Kawamura and M. Enoeda Outline DEMO blankets
More informationImproved Design of a Helium- Cooled Divertor Target Plate
Improved Design of a Helium- Cooled Divertor Target Plate By X.R. Wang, S. Malang, R. Raffray and the ARIES Team ARIES-Pathway Meeting University of Wisconsin, Madison April 23-24, 2009 Critical Design
More informationBenchmark Evaluation of Reactivity Measurements for Beryllium- Reflected Space Reactor Mockup
Benchmark Evaluation of Reactivity Measurements for Beryllium- Reflected Space Reactor Mockup Margaret A. Marshall Idaho National Laboratory John D. Bess Idaho National Laboratory NETS 2015 NETS 2014 Infinity
More informationIndustrialization process
Industrialization process Power couplers for XFEL project as an example ------------ Serge Prat TESLA meeting - 30 March 2005 1/41 Industrialization: Why? Start: Prototypes Quality: - uneven ( 30 Couplers)
More informationSafety Analysis of the US Dual Coolant Liquid Lead Lithium ITER Test Blanket Module
Safety Analysis of the US Dual Coolant Liquid Lead Lithium ITER Test Blanket Module Brad Merrill 1, Susana Reyes 2, Mohamed Sawan 3, and Clement Wong 4 1 Idaho National Laboratory, Idaho Falls, ID, USA,
More informationOccupational Radiation Exposure (ORE) Dose Rate for TBM Replacement/Maintenance and Improving Estimates by 3-D Calculations
Occupational Radiation Exposure (ORE) Dose Rate for TBM Replacement/Maintenance and Improving Estimates by 3-D Calculations Mahmoud Youssef Mohamed Dagher UCLA With input from Brad Merrill (INL) FNST Meeting,
More informationRisk and Opportunity Management - Overview
Risk and Opportunity Management - Overview Webinar Learning Objectives At the end of this Webinar, you will: Understand the 5 step Risk and Opportunity Management (R&OM) process Recognize R&OM as a tool
More informationOverview of the Lead-Lithium Ceramic Breeder (LLCB) Test Blanket Module (TBM) activities in India. A.K. Suri, T. Jayakumar and E.
Overview of the Lead-Lithium Ceramic Breeder (LLCB) Test Blanket Module (TBM) activities in India A.K. Suri, T. Jayakumar and E. Rajendrakumar Lead-Lithium cooled Ceramic Breeder (LLCB) U-shaped First
More informationSummary of Task B Activities*
Summary of Task B Activities* R. Kaita and R. Woolley Princeton Plasma Physics Laboratory APEX Electronic Meeting 20 13 and 15 August 2002 *with contributions from M. Ulrickson, B. Nelson, A. Hassanein,
More informationProspects of new ODS steels
Prospects of new ODS steels Annual Fusion Seminar VTT Tampere, June 2-3, 2010 Seppo Tähtinen VTT Technical Research Centre of Finland 6/3/2010 2 Fusion advantages Unlimited fuel No CO 2 or air pollution
More informationConcept of Multi-function Fusion Reactor
Concept of Multi-function Fusion Reactor Songtao WU, Yican WU, Hongli CHEN, Songlin LIU, Jiangang LI, Yuanxi WAN Institute of Plasma Physics, Chinese Academy of Sciences, Hefei, P.R. China stwu@ipp.ac.cn
More informationSYSTEMATIC APPROACH FOR DECOMMISSIONING PLANNING AND ESTIMATING
ABSTRACT SYSTEMATIC APPROACH FOR DECOMMISSIONING PLANNING AND ESTIMATING A. Scott Dam, P. E. JUPITER Corporation 2730 University Boulevard West, Suite 900 Wheaton, MD 20702 Nuclear facility decommissioning,
More informationTechnical 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)
More informationMultiple Effects/ Multiple Interactions and the Need for Fusion Nuclear Science Facility prior to construction of DEMO
Multiple Effects/ Multiple Interactions and the Need for Fusion Nuclear Science Facility prior to construction of DEMO Issues, Role, Design Features, and R&D requirements Mohamed Abdou Distinguished Professor
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 informationFUSION TECHNOLOGY INSTITUTE
FUSION TECHNOLOGY INSTITUTE Two-Dimensional Nuclear Analysis in Support of ITER Blanket Module Design W I S C O N S I N M.E. Sawan May 2011 UWFDM-1393 FUSION TECHNOLOGY INSTITUTE UNIVERSITY OF WISCONSIN
More informationMORS Introduction to Cost Estimation (Part I)
MORS Introduction to Cost Estimation (Part I) Mr. Huu M. Hoang Slide 1 Disclosure Form Slide 2 Learning Objectives of Module Two 1. Understand how to define a program using the various documents and other
More informationKey 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,
More informationTechnology R&D Activities for the ITER full-tungsten Divertor
1 ITR/2-3 Technology R&D Activities for the ITER full-tungsten Divertor P. Lorenzetto 1, M. Bednarek 1, F. Escourbiac 2, P. Gavila 1, T. Hirai 2, N. Litunovsky 3, A. Makhankov 3, S. Mazaev 3, I. Mazul
More informationUpdate on APEX Safety Issues
Update on APEX Safety Issues Presented by: K. A. McCarthy With contributions by: L. C. Cadwallader, K. A. McCarthy, B. J. Merrill, and R. L. Moore Fusion Safety Program APEX Meeting May 12-14, 1999 PPPL
More informationIntroduction to Cost Estimation - Part I
Introduction to Cost Estimation - Part I Best Practice Checklists Best Practice 1: Estimate Purpose and Scope The estimate s purpose is clearly defined The estimate s scope is clearly defined The level
More informationScientific Framework for Advancing Blanket/FW/Tritium Fuel Cycle Systems towards FNSF & DEMO Readiness
Scientific Framework for Advancing Blanket/FW/Tritium Fuel Cycle Systems towards FNSF & DEMO Readiness Input to FESAC Strategic Plan Panel Gaithersburg, Washington, June 3, 2014 (Greenwald Gaps G11, G12
More informationConsideration of Alumina Coating Fabricated by Sol-gel Method as MHD Coating against PbLi
Consideration of Alumina Coating Fabricated by Sol-gel Method as MHD Coating against PbLi Y. Ueki and T. Kunugi Department of Nuclear Engineering, Kyoto University Yoshida, Sakyo, Kyoto, JAPAN 606-8501
More informationAdvanced Study of a Tokamak Transmutation System
Abstract Advanced Study of a Tokamak Transmutation System L. J. Qiu, Y. C. Wu, B. Wu, X.P. Liu, Y.P. Chen, W.N. Xu, Q.Y. Huang Institute of Plasma Physics, Chinese Academy of Sciences P.O. Box 1126, Hefei,
More informationTask III presentations
Task III presentations Nelson (ORNL) Nygren (SNL) Rognlien (LLNL) Youssef (UCLA) Smolentsev (UCLA) ALL Sn-CLiFF Configuration and Status (15 min.) Divertor Integration Status (20 min) FW and Diveror Temperature
More informationBlanket/First Wall Challenges and Required R&D on the pathway to DEMO
Blanket/First Wall Challenges and Required R&D on the pathway to DEMO Mohamed Abdou, Neil Morley, Alice Ying, Sergey Smolentsev Fusion Science and Technology Center, UCLA Barceloneta, Barcelona ISFNT 11
More informationGLAST LAT Project Integration and Test CDR Peer Review, March 28,
Gamma-ray Large Area Space Telescope GLAST Large Area Telescope: I & T Peer Review Summary Elliott Bloom SU-SLAC Subsystem Manager elliott@slac.stanford.edu 650-926-2469 Document: LAT-PR-01779-01 Section
More informationAdvancements in Laser Welding Technology
June 015 [Volume 1, Issue 1] Advancements in Laser Welding Technology Broadening our Horizons Contents Special Interest Articles We are proud to announce the Broadening our Horizons 1 purchase of a brand
More informationDevelopment of a Large-scale Monoblock Divertor Mock-up for Fusion Experimental Reactors in JAERI
Development of a Large-scale Monoblock Divertor Mock-up for Fusion Experimental Reactors in JAERI S. Suzuki, K. Sato, K. Ezato, M. Taniguchi, M. Akiba Japan Atomic Energy Research Institute, Ibaraki-ken,
More informationTitle: Rectification of 20/90 Dragline. B Prabhakar Rao Manager, Coal and Coke Oven(C-1), MECON Limited, Ranchi.
Title: Rectification of 20/90 Dragline By B Prabhakar Rao Manager, Coal and Coke Oven(C-1), MECON Limited, Ranchi. Dragline: Walking dragline 20/90 manufactured in collaboration with Russia is a powerful
More informationFlorida Department of Education Student Performance Standards Welding Technology Fundamentals Course
A Correlation of to the Florida Department of Education Student Performance Standards Welding Technology Fundamentals Course 9204400 Page 1 of 18 SUBJECT: Career and Technical Education GRADE LEVEL: 9-12
More informationGerhart Grinanger, NOELL GmbH, Postfach 6260, D-8700 Wizrzburg, Germany
861 REMOTELY-OPERATED DISMANTLING OF THE REACTOR INTERNALS AT NIEDERAICHBACH POWER PLANT USING MANIPULATORS Gerhart Grinanger, NOELL GmbH, Postfach 6260, D-8700 Wizrzburg, Germany ABSTRACT The joint venture
More informationCom-Tray. Under Floor
Com-Tray Chalfant, a leading supplier of cable trays and systems for utilities, industrial plants, and commercial service, offers Com-Tray, a unique modular, cost-saving system for routing and protecting
More informationAgeing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants
DS485 17 July 2017 IAEA SAFETY STANDARDS for protecting people and the environment STEP 13: Establishment by the Publications Committee Reviewed in NSOC (Asfaw) Ageing Management and Development of a Programme
More informationDIVISION 15-MECHANICAL SECTION SUPPORTS AND ANCHORS PN PART 1 - GENERAL 1.01 SECTION INCLUDES. A. Pipe and equipment support systems.
PART 1 - GENERAL 1.01 SECTION INCLUDES A. Pipe and equipment support systems. B. Inserts. 1.02 RELATED SECTIONS A. Section 15890 - Ductwork Supports. 1.03 DEFINITIONS A. Supports: Attachments, hangers,
More informationDEMO Concept Development and Assessment of Relevant Technologies
1 FIP/3-4Rb DEMO Concept Development and Assessment of Relevant Technologies Y. Sakamoto, K. Tobita, H. Utoh, N. Asakura, Y. Someya, K. Hoshino, M. Nakamura, S. Tokunaga and the DEMO Design Team Japan
More informationSurvey 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
More informationITER The way to a benign and limitless new energy
ITER The way to a benign and limitless new energy source A global collaboration has been formed to test the feasibility of fusion Page 1 ITR/1-1 Preparations of the ITER Vacuum Vessel Construction 11 October,
More informationITER The way to a benign and limitless new energy
ITER The way to a benign and limitless new energy source A global collaboration has been formed to test the feasibility of fusion Page 1 ITR/1-1 Preparations of the ITER Vacuum Vessel Construction 11 October,
More informationGrading of the Management System Requirements to the Safe
Grading of the Management System Requirements to the Safe Transport of Radioactive Materials Y.E. Tawfik ETRR-2 Complex, Egyptian Atomic Energy Authority, Cairo Egypt Received: 1/3/2016 Accepted: 7/6/2016
More informationStellarators difficult to build? The construction of Wendelstein 7-X
Seminar @ ITER Stellarators difficult to build? The construction of Wendelstein 7-X Thomas Klinger Max-Planck Institute for Plasma Physics, Greifswald on behalf of the enterprise Wendelstein 7-X ITER Seminar,
More informationAchievements 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
More informationTutorial for Jacketed Piping Modeling and Analysis using CAEPIPE
Tutorial for Jacketed Piping Modeling and Analysis using CAEPIPE The following are the Steps to perform Jacketed Piping Modeling and Analysis using CAEPIPE. General Jacketed piping is used when the primary
More informationWBS WBS Title WBS Dictionary Description Tracker Tracker Management UCSC: Provide for analysis of scientific requirements relative to
WBS WBS Title WBS Dictionary Description 4.1.4 Tracker 4.1.4.1 Tracker Management UCSC: Provide for analysis of scientific requirements relative to the design of the Tracker. Support the development of
More informationUltrasonic Inspection of High Heat Flux (HHF) Tested Tungsten Monoblock Type Divertor Test Mock ups
National Seminar & Exhibition on Non-Destructive Evaluation, NDE 2014, Pune, December 4-6, 2014 (NDE-India 2014) Vol.20 No.6 (June 2015) - The e-journal of Nondestructive Testing - ISSN 1435-4934 www.ndt.net/?id=17850
More informationTechnical Summary for TCC0 Global overview of the scope for TCC0 contract
IDM UID V89YJN VERSION CREATED ON / VERSION / STATUS 06 Oct 2017 / 2.0 / Signed EXTERNAL REFERENCE / VERSION Technical Specification Technical Summary for TCC0 Global overview of the scope for TCC0 contract
More informationDevelopment of High Heat Flux Components in JAERI
US-Japan Workshop on Fusion High Power Density Device and Design, UCLA, February, 16-19, 1999 Development of High Heat Flux Components in JAERI K. Ezato, NBI Heating Lab., Dept. Of Fusion Engineering,
More informationReplacement Works for the Steam Generator and the Reactor Pressure Vessel Upper Head
Unit 2, Genkai Nuclear Power Plant Replacement Works for the Steam Generator and the Reactor Pressure Vessel Upper Head Replacement works for the above components were conducted at Unit 2 of the Genkai
More informationR & D of the Fabrication Technology for ITER Magnet Supports
ITR/P1-45 R & D of the Fabrication Technology for ITER Magnet Supports 1 P. Y. Lee*, 1 C.J.Pan, 1. L. Hou, 1 S.L.Han, 1 Z.C.Sun, 1 X. R. Duan, 1 Y. Liu, 2 F. Savary, 2 Y. K. Fu and 2 R. Gallix, 2 N. Mitchell
More informationSafety 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
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 information