Neutronics Analysis for K-DEMO Blanket Module with Helium coolant June 26, 2013 Presented by Kihak IM Prepared by Y.S. Lee Fusion Engineering Center DEMO.

Slides:



Advertisements
Similar presentations
First Wall Heat Loads Mike Ulrickson November 15, 2014.
Advertisements

Scoping Neutronics Analysis in Support of FDF Design Evolution Mohamed Sawan University of Wisconsin-Madison With input from R. Stambaugh, C. Wong, S.
PhD studies report: "FUSION energy: basic principles, equipment and materials" Birutė Bobrovaitė; Supervisor dr. Liudas Pranevičius.
Conceptual design of a demonstration reactor for electric power generation Y. Asaoka 1), R. Hiwatari 1), K. Okano 1), Y. Ogawa 2), H. Ise 3), Y. Nomoto.
Thermo Fluid Design Analysis of TBM cooling schemes M. Narula with A. Ying, R. Hunt, S. Park ITER-TBM Meeting UCLA Feb 14-15, 2007.
What is Dual Coolant Blanket? Siegfried Malang 2 nd EU-US DCLL Workshop2 nd EU-US DCLL Workshop University of California,University of California, Los.
09 FNST meeting Preliminary Neutronics Analysis for IB Shielding Design on FNSF (Standard Aspect Ratio) Haibo Liu Robert Reed Fusion Science and Technology.
Japan-US Workshop held at San Diego on April 6-7, 2002 How can we keep structural integrity of the first wall having micro cracks? R. Kurihara JAERI-Naka.
Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Japan-US FPP-Workshop with EU participation, January 11-13, 2005, Tokyo EU PPCS Models C&D P.
Presented by: S. Suzuki, Blanket Engineering Lab., Japan Atomic Energy Research Institute, JAERI Contents 1.Outline of blanket development in JAERI 2.Design.
Neutronics Analysis on a Compact Tokamak Fusion Reactor CREST Q. HUANG 1,2, S. ZHENG 2, L. Lu 2, R. HIWATARI 3, Y. ASAOKA 3, K. OKANO 3, Y. OGAWA 1 1 High.
FNSF Blanket Testing Mission and Strategy Summary of previous workshops 1 Conclusions Derived Primarily from Previous FNST Workshop, August 12-14, 2008.
Fusion Neutronics Activities in USA Reported for the Neutronics Groups at UCLA, UW, and TSI Research, Inc. by E.T. Cheng TSI Research, Inc. P.O. Box 2754.
June 14-15, 2006/ARR 1 ARIES-CS Power Core Engineering: Updating Power Flow, Blanket and Divertor Parameters for New Reference Case (R = 7.75 m, P fusion.
Status of the Modular and Field- Period Replacement Maintenance Presented by X.R. Wang Contributors: S. Malang, A.R. Raffray and L. El-Guebaly ARIES Meeting.
January 11-13, 2005/ARR 1 Ceramic Breeder Blanket Coupled with Brayton Cycle Presented by: A. R. Raffray (University of California, San Diego) With contributions.
August 17, 2000 ARIES: Fusion Power Core and Power Cycle Engineering/ARR 1 ARIES: Fusion Power Core and Power Cycle Engineering The ARIES Team Presented.
Poloidal Distribution of ARIES-ACT Neutron Wall Loading L. El-Guebaly, A. Jaber, D. Henderson Fusion Technology Institute University of Wisconsin-Madison.
Ceramic Breeder Blanket Conceptual Design for ARIES-CS Contributors: S. Malang, A.R. Raffray, and L. El-Guebaly ARIES Meeting University of Wisconsin,
ARIES-CS Systems Studies J. F. Lyon, ORNL Workshop on Fusion Power Plants UCSD Jan. 24, 2006.
US DEMO MS FW / Blanket Assessment Blanket Design Concepts Prepared by Paul Fogarty, Siegfried Malang Mo Dagher With contributions from the US MS DEMO.
Status of 3-D Analysis, Neutron Streaming through Penetrations, and LOCA/LOFA Analysis L. El-Guebaly, M. Sawan, P. Wilson, D. Henderson, A. Ibrahim, G.
The main function of the divertor is minimizing the helium and impurity content in the plasma as well as exhausting part of the plasma thermal power. The.
June19-21, 2000Finalizing the ARIES-AT Blanket and Divertor Designs, ARIES Project Meeting/ARR ARIES-AT Blanket and Divertor Design (The Final Stretch)
A design for the DCLL inboard blanket S. Smolentsev, M. Abdou, M. Dagher - UCLA S. Malang – Consultant, Germany 2d EU-US DCLL Workshop University of California,
March 20-21, 2000ARIES-AT Blanket and Divertor Design, ARIES Project Meeting/ARR Status ARIES-AT Blanket and Divertor Design The ARIES Team Presented.
Y. ASAOKA, R. HIWATARI and K
Minimum Radial Standoff: Problem definition and Needed Info L. El-Guebaly Fusion Technology Institute University of Wisconsin - Madison With Input from:
The effect of the orientations of pebble bed in Indian HCSB Module Paritosh Chaudhuri Institute for Plasma Research Gandhinagar, INDIA CBBI-16, Sept.
Development of the FW Mobile Tiles Concept Mohamed Sawan, Edward Marriott, Carol Aplin University of Wisconsin-Madison Lance Snead Oak Ridge National Laboratory.
Overview of LLCB TBM for ITER Paritosh Chaudhuri Institute for Plasma Research Gandhinagar, INDIA CBBI-16, Sept. 2011, Portland, USA.
1 Recent Progress in Helium-Cooled Ceramic Breeder (HCCB) Blanket Module R&D and Design Analysis Ying, Alice With contributions from M. Narula, H. Zhang,
ASIPP EAST Overview Of The EAST In Vessel Components Upgraded Presented by Damao Yao.
Fusion-Fission Hybrid Systems
Fusion Blanket Technology
Neutronics Parameters for Preferred Chamber Configuration with Magnetic Intervention Mohamed Sawan Ed Marriott, Carol Aplin UW Fusion Technology Inst.
October 27-28, 2004 HAPL meeting, PPPL 1 Thermal-Hydraulic Analysis of Ceramic Breeder Blanket and Plan for Future Effort A. René Raffray UCSD With contributions.
HCCB TBM Mechanical Design R. Hunt, A. Ying, M. Abdou Fusion Science & Technology Center University of California Los Angeles May 11, 2006 Presented by.
1 Preliminary Design of China ITER TBM with Helium-Cooled and Solid Breeder Concept Preliminary Design of China ITER TBM with Helium-Cooled and Solid Breeder.
Three-Dimensional Nuclear Analysis for the US DCLL TBM M. Sawan, B. Smith, E. Marriott, P. Wilson University of Wisconsin-Madison With input from M. Dagher.
Design study of advanced blanket for DEMO reactor US/JP Workshop on Fusion Power Plants and Related Advanced Technologies 23 th -24 th Feb at UCSD,
ITER test plan for the solid breeder TBM Presented by P. Calderoni March 3, 2004 UCLA.
U PDATED ARIES-ACT P OWER C ORE D EFINITION AND S I C B LANKET X.R. Wang, M. S. Tillack, S. Malang F. Najmabadi and L.A. El-Guebaly ARIES-Pathways Project.
Systems Code – Hardwired Numbers for Review C. Kessel, PPPL ARIES Project Meeting, July 29-30, 2010.
1 Neutronics Assessment of Self-Cooled Li Blanket Concept Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI With contributions.
1 Neutronics Parameters for the Reference HAPL Chamber Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI With contributions.
Base Breeding Blanket and Testing Strategy In FNF Conclusions Derived from Previous FNST Workshop, August 12-14, 2008.
Forschungszentrum Karlsruhe FZK - EURATOM ASSOCIATION 05/14/2005 Thomas Ihli 1 Status of He-cooled Divertor Design Contributors: A.R. Raffray, and The.
Update on ARIES ACT2 Power Core Design and Engineering X. R. Wang, M. S. Tillack, C. Koehly ARIES Project Meeting 18 September2013 ARIES UC San Diego UW.
Systems Analysis Development for ARIES Next Step C. E. Kessel 1, Z. Dragojlovic 2, and R. Raffrey 2 1 Princeton Plasma Physics Laboratory 2 University.
1 Nuclear Assessment of HAPL Chamber with Magnetic Intervension Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI With contributions.
March 3-4, 2005 HAPL meeting, NRL 1 Assessment of Blanket Options for Magnetic Diversion Concept A. René Raffray UCSD With contributions from M. Sawan.
1 Radiation Environment at Final Optics of HAPL Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI HAPL Meeting ORNL March.
Summary of Nuclear Input for Safety Analysis for the DCLL TBM -update-
ARIES Pathways Project 05/29/08
DCLL TBM Reference Design
X.R. Wang, M. S. Tillack, S. Malang, F. Najmabadi and the ARIES Team
Design Concept of K-DEMO for Near-Term Implementation
Can We achieve the TBR Needed in FNF?
University of California, San Diego
CERAMIC BREEDER BLANKET FOR ARIES-CS
Trade-Off Studies and Engineering Input to System Code
CERAMIC BREEDER BLANKET FOR ARIES-CS
Current Status of Chinese HCCB TBM Program
Comments on ARIES-ACT 10/20/2010 Pre-Strawman
Contributors: Wei Zhang, M. Z. Youssef, A. Ying
CERAMIC BREEDER BLANKET FOR ARIES-CS
Updated DCLL TBM Neutronics Analysis
Summary slide for Conceptual Design Study for Heat Exhaust Management in the ARC Fusion Pilot Plant, E.A. Tolman et al., IAEA- FIP-P1-22 Introduction ARC,
Nuclear Analyses for two “Look-alike” HCPB Blanket Sub-modules for Testing in ITER Mahmoud Z Youssef UCLA Presented at ITER-TBM4 Meeting, UCLA, March 2-4,
Presentation transcript:

Neutronics Analysis for K-DEMO Blanket Module with Helium coolant June 26, 2013 Presented by Kihak IM Prepared by Y.S. Lee Fusion Engineering Center DEMO Technology Division / In-Vessel Component Team PPPL-NFRI Meeting, June 26-28, 2013, at PPPL

Thickness of Blanket Layers in the Current K-DEMO  Inboard Blanket [Thickness = 1,050 mm]  Outboard Blanket [Thickness = 1,200 mm] W Li 4 SiO 4 Cooling channel Be B4CB4C Structural Material W FW – 4 mm RAFM ~ 15 mm He Channel ~ 10 mm RAFM – 2 mm Ceramic pebble breeder Manifold & Structures Shield Inb. Blanket Be 31 FW Be Manifold & Structures Shield Outb. Blanket Be 31 FW Be 50

Concept of Blanket (One Module) Cooling Channel  FW requires a dedicated cooling channel…. Maximum neutron wall load area The other 8 cooling channels, 6 mm wide each, have common inlet/outlet (Peak) 3 MW/m 2 neutron wall load + ~0.5 MW/m 2 radiation heat load (f core_rad = 0.5)

Neutronic Analysis Model for Inboard/Outboard Blanket (One Module) for Thickness Optimization between Layers Thickness of Layer (cm) Accumulated Thickness (cm) FW0.4 Cooling Channel2.7 ( ) st Breeder Cooling Channel1.2 ( ) nd Breeder Cooling Channel1.2 ( ) st Be Cooling Channel1.0 ( ) rd Breeder Cooling Channel1.0 ( ) th Breeder Cooling Channel1.0 ( ) nd Be Cooling Channel1.0 ( ) th Breeder Cooling Channel1.0 ( ) rd Be Cooling Channel0.8 ( ) MW neutron (max.) = 2.13x10 18 n/s [unit in cm] Shielding behind the breeding blanket is not included yet.

Neutronics Analysis  Accumulated TBR = (for one module) [unit in cm] Neutron Reflection B.C. at sides (Minor) Neutron penetration at back side Neutron Back-scattering at front (~10% ?) If neutron back-scattering at front is counted in, TBR could be increased by ~10% (?).  3D full sector model is required to get reliable TBR  3D sector model is under construction… NOT ENOUGH to meet global TBR >1, considering non-breeding zone, such as divertor and ports.

Generated Heat in the individual layer (for NWL = 3 MW) 3.3 MW (Energy multiplication factor = 1.1) Could be increased if back-scattered neutrons are counted in Be Li Breeder  Important data for cooling design Some heat generation in W and RAFM

Power density in the HCCB module Tungsten Li-breeder (exo-thermic reaction) Power density is higher in tungsten and Li-breeding zones

Future Work  Shielding will be added and optimized.  Model expansion is on-going to cover 3-D, 22.5 degree toroidal sector of both inboard and outboard blankets, to consider the reflected neutrons and global TBRs.  will give more reliable global TBR…  T-H analyses are on-going in parallel at the moment for appropriate cooling design.