'Nuclear heating' diaporamas de présentation

Fusion Neutronics - Methods, Data, Applications -

952 views • 92 slides

FIRE Vacuum Vessel and Remote Handling Overview

FIRE Vacuum Vessel and Remote Handling Overview B. Nelson, T. Burgess, T. Brown, D. Driemeyer, H-M Fan, K. Freudenberg, G. Jones, C. Kessel, P. Ryan, M. Sawan, M. Ulrickson, D. Strickler, D. Williamson FIRE Physics Validation Review March 31, 2004 Presentation Outline Vacuum Vessel

985 views • 57 slides

Status of US ITER Neutronics Activities

Status of US ITER Neutronics Activities. Outline Examples of US activities during EDA US ITER neutronics activities in the past year Possible future US contribution to ITER neutronics activities. US Neutronics Computation Capabilities.

346 views • 34 slides

ITER In-Vessel Coils (IVC) Interim Design Review Thermal Structural FEA of Feeders

ITER In-Vessel Coils (IVC) Interim Design Review Thermal Structural FEA of Feeders. A Brooks July 27, 2010. Middle and Lower ELM Feeders Analysis Status Overview. Geometry Modeling & Meshing Feeders Background Field Coils Material Properties Boundary Conditions Temperature

407 views • 28 slides

Status of US ITER Neutronics Activities

Status of US ITER Neutronics Activities. Outline Examples of US activities during EDA US ITER neutronics activities in the past year Possible future US contribution to ITER neutronics activities. US Neutronics Computation Capabilities.

374 views • 27 slides

Design of the ITER Magnets to Provide Plasma Operational Flexibility

Design of the ITER Magnets to Provide Plasma Operational Flexibility N. Mitchell, D. Bessette, M. Ferrari, M. Huguet, C. Jong, Y. Takahashi, K. Yoshida 1) R. Maix 2) Y. Krivchenkov, E. Zapretilina 3) 1) ITER IT, Naka and Garching JWS 2) ATI Atominstitut Wien, Austria

368 views • 23 slides

Design study of advanced blanket for DEMO reactor

US/JP Workshop on Fusion Power Plants and Related Advanced Technologies 23 th -24 th Feb. 2010 at UCSD, U.S.A. Design study of advanced blanket for DEMO reactor. JAEA Hiroyasu Utoh. Outline. Water-cooled LiPb BLK 2-D BLK analysis code He cooling system. 1. Introduction. PPCS (modelC).

327 views • 15 slides

Fusion Nuclear Science and Technology (FNST) Challenges and Facilities on the Pathway to Fusion Energy

Fusion Nuclear Science and Technology (FNST) Challenges and Facilities on the Pathway to Fusion Energy.

314 views • 14 slides

LOCA/LOFA Analyses for LiPb/FS System

LOCA/LOFA Analyses for LiPb/FS System. Carl Martin, Jake Blanchard Fusion Technology Institute University of Wisconsin - Madison ARIES-CS Project Meeting November 4-5, 2004. LOCA/LOFA Analysis Update.

272 views • 14 slides

Neutronic Calculations for LH launcher in ITER equatorial port

A. s. s. o. c. i. a. z. i. o. n. e. E. U. R. A. T. O. M. E. N. E. A. s. u. l. l. a. F. u. s. i. o. n. e. EFDA task HCD-08-03. Neutronic Calculations for LH launcher in ITER equatorial port. R. Villari UT-FUSTEC ENEA CR Frascati.

201 views • 11 slides