LLNL Chambers Activities Presented by: Jeff Latkowski Chambers Team: Ryan Abbott, Alison Kubota, Wayne Meier, Susana Reyes April 10, 2003 Work performed.

Slides:

Advertisements

Similar presentations

Development of analytical bond- order potentials for the Be-C-W-H system C. Björkas, N. Juslin, K. Vörtler, H. Timkó, K. Nordlund Department of Physics,

Advertisements

NEEP 541 – Creep Fall 2002 Jake Blanchard.

September 24-25, 2003 HAPL meeting, UW, Madison 1 Armor Configuration & Thermal Analysis 1.Parametric analysis in support of system studies 2.Preliminary.

NEEP 541 – Defects Fall 2003 Jake Blanchard. Outline Irradiation Induced Defects Definitions Particles Cascades Depleted zones Thermal Spikes.

Dynamic hydrogen isotope behavior and its helium irradiation effect in SiC Yasuhisa Oya and Satoru Tanaka The University of Tokyo.

Y. Ueda, M. Fukumoto, H. Kashiwagi, Y. Ohtsuka (Osaka University)

Views on Neutronics and Activation Issues Facing Liquid-Protected IFE Chambers L. El-Guebaly and the ARIES Team Fusion Technology Institute University.

Wayne R. Meier Lawrence Livermore National Lab Heavy Ion Fusion Modeling Update - Spot Size Model Changes* ARIES Meeting April 22-23, 2002 * This work.

Wayne R. Meier Lawrence Livermore National Lab Heavy Ion Fusion Modeling Update* ARIES e-Meeting October 17, 2001 * This work was performed under the auspices.

Design Considerations for Beam Port Insulator Rings

ARIES Meeting April 22-23, 2002 U. Wisconsin, Madison Work performed under the auspices of the U. S. Department of Energy by University of California Lawrence.

Status of safety analysis for HCPB TBM Susana Reyes TBM Project meeting, UCLA, Los Angeles, CA May 10-11, 2006 Work performed under the auspices of the.

EFFECTS OF CHAMBER GEOMETRY AND GAS PROPERTIES ON HYDRODYNAMIC EVOLUTION OF IFE CHAMBERS Zoran Dragojlovic and Farrokh Najmabadi University of California.

Impact of Liquid Wall on Fusion Systems Farrokh Najmabadi University of California, San Diego NRC Fusion Science Assessment Committee November 17, 1999.

November 8-9, Blanket Design for Large Chamber A. René Raffray UCSD With contributions from M. Sawan (UW), I. Sviatoslavsky (UW) and X. Wang (UCSD)

Action Items For ARIES-IFE Study Farrokh Najmabadi ARIES Project Meeting June 19-21, 2000 University of Wisconsin, Madison Electronic copy:

Safety assessment for Safety assessment for potential target materials: radioactivity vs. chemical toxicity presented by: Susana Reyes ARIES Group Meeting.

Findings and Recommendations from Wetted-Wall IFE Designs Jeff Latkowski Lawrence Livermore National Laboratory March 9, 2001 Work performed under the.

October 24, Remaining Action Items on Dry Chamber Wall 2. “Overlap” Design Regions 3. Scoping Analysis of Sacrificial Wall A. R. Raffray, J.

Progress Report on Chamber Dynamics and Clearing Farrokh Najmabadi, Rene Raffray, Mark S. Tillack, John Pulsifer, Zoran Dragovlovic (UCSD) Ahmed Hassanein.

Laser IFE Program Workshop –5/31/01 1 Output Spectra from Direct Drive ICF Targets Laser IFE Workshop May 31-June 1, 2001 Naval Research Laboratory Robert.

Comparative Analysis of Microstructural Defects in Monocrystalline Copper: Shock Compression Versus Quasi-isentropic Compression H. Jarmakani, M. Meyers,

Nov 13-14, 2001 A. R. Raffray, et al., Progress Report on Chamber Clearing Code Effort 1 Progress Report on Chamber Clearing Code Development Effort A.

Shielding of the Final Focusing System in the HIF Point Design* by Jeff Latkowski and Wayne Meier ARIES Projct Meeting January 8-9, 2003 *Work performed.

1 ARIES IFE - Some Concluding Comments on Thick Liquid Walls Wayne Meier, Ryan Abbott, Jeff Latkowski, Ralph Moir, Susana Reyes ARIES Project Meeting September.

Wayne R. Meier Lawrence Livermore National Lab Per Peterson UC Berkeley Updated Heavy Ion Driver Parameters for Snowmass Point Design ARIES Meeting July.

Oxidation of Graphite Walls: Preliminary Results from SOMBRERO Safety Analysis S. Reyes, J. F. Latkowski Lawrence Livermore National Laboratory Laser IFE.

Wayne R. Meier Lawrence Livermore National Lab Heavy Ion Driver Model Update* ARIES IFE Meeting LLNL March 8-9, 2001 * This work was performed under the.

RRP:10/17/01Aries IFE 1 Liquid Wall Chamber Dynamics Aries Electronic Workshop October 17, 2001 Robert R. Peterson Fusion Technology Institute University.

M. Yoda, S. I. Abdel-Khalik, D. L. Sadowski and M. D. Hageman Woodruff School of Mechanical Engineering Extrapolating Experimental Results for Model Divertor.

Accident assessment for DCLL DEMO design Susana Reyes TBM Project meeting, UCLA, Los Angeles, CA March 2-4, 2005 Work performed under the auspices of the.

HAPL WORKSHOP Chamber Gas Density Requirements for Ion Stopping Presented by D. A. Haynes, Jr. for the staff of the Fusion Technology Institute.

Systems Modeling Update including Magnetic Deflection HAPL Program Meeting General Atomics August 8-9, 2006 Wayne Meier LLNL Work performed under the auspices.

Measurement and modeling of hydrogenic retention in molybdenum with the DIONISOS experiment G.M. Wright University of Wisconsin-Madison, FOM – Institute.

Long Term Exposure of Candidate First Wall Materials on XAPPER February – May 2004 Presented by: Jeff Latkowski XAPPER Team: Ryan Abbott, Robert Schmitt,

M. Yoda, S. I. Abdel-Khalik, D. L. Sadowski, B. H. Mills, and J. D. Rader G. W. Woodruff School of Mechanical Engineering Updated Thermal Performance of.

“Influence of atomic displacement rate on radiation-induced ageing of power reactor components” Ulyanovsk, 3 -7 October 2005 Displacement rates and primary.

Overview of ‘classical’ or ‘standardized’ DPA calculation stemming from the reactor world. Colin English NNL.

Ion Mitigation for Laser IFE Optics Ryan Abbott, Jeff Latkowski, Rob Schmitt HAPL Program Workshop Los Angeles, California, June 2, 2004 This work was.

Plan to Develop A First Wall Concept for Laser IFE.

Ionic Conductors: Characterisation of Defect Structure Lecture 15 Total scattering analysis Dr. I. Abrahams Queen Mary University of London Lectures co-financed.

Atomic scale understandings on hydrogen behavior in Li 2 O - toward a multi-scale modeling - Satoru Tanaka, Takuji Oda and Yasuhisa Oya The University.

This work was performed under the auspices of the U.S. Department of Energy by University of California Lawrence Livermore National Laboratory under Contract.

UCRL-PRES Magnet Design Considerations & Efficiency Advantages of Magnetic Diversion Concept W. Meier & N. Martovetsky LLNL HAPL Program Meeting.

Laser IFE Meeting November 13-14, 2001 Crowne Plaza Hotel, Pleasanton, CA Work performed under the auspices of the U. S. Department of Energy by University.

July 11, 2003 HAPL e-meeting. 1 Armor Design & Modeling Progress A. René Raffray UCSD HAPL e-meeting July 11, 2003 (1)Provide Parameters for Chamber “System”

ELECTRONIC STRUCTURE OF MATERIALS From reality to simulation and back A roundtrip ticket.

Atomistic Simulations of Damage in Silica Glass and Graphite Due to Irradiation Alison Kubota 1, Maria-Jose Caturla 1, Tomas Diaz de la Rubia 1, Stephen.

1 Neutronics Assessment of Self-Cooled Li Blanket Concept Mohamed Sawan Fusion Technology Institute University of Wisconsin, Madison, WI With contributions.

The effect of displacement damage on deuterium retention in plasma-exposed tungsten W.R.Wampler, Sandia National Laboratories, Albuquerque, NM R. Doerner.

Progress in Alternate Chambers Activities presented by: Jeff Latkowski contributors: Don Blackfield, Wayne Meier, Ralph Moir, Charles Orth, Susana Reyes,

XAPPER Progress on the First Wall Battle Plan Presented by: Jeff Latkowski XAPPER Team: Ryan Abbott, Wilburt Davis, Steve Payne, Susana Reyes, Joel Speth.

Temperature Response and Ion Deposition in the 1 mm Tungsten Armor Layer for the 10.5 m HAPL Target Chamber T.A. Heltemes, D.R. Boris and M. Fatenejad,

Effect of Re Alloying in W on Surface Morphology Changes After He + Bombardment at High Temperatures R.F. Radel, G.L. Kulcinski, J. F. Santarius, G. A.

Laser-Assisted Particle Removal

Highlights Highlights of HEROS : First RT model to include spatial dependency of microstructure Ability to model Free-Surfaces implantation, and temperature.

The Neutronics of Heavy Ion Fusion Chambers Jeff Latkowski and Susana Reyes 15 th Heavy Ion Inertial Fusion Symposium Princeton, NJ June 9, 2004 Work performed.

Target threat spectra Gregory Moses and John Santarius with Thad Heltemes, Milad Fatenejad, Matt Terry and Jiankui Yuan Fusion Technology Institute University.

NEEP 541 – Swelling Fall 2002 Jake Blanchard. Outline Swelling.

Diffusion Chapter 5. Mechanics of Diffusion Primary method by which atoms mix Consider a drop of food coloring in a glass of water.

Ion Mitigation for Laser IFE Optics Ryan Abbott, Jeff Latkowski, Rob Schmitt HAPL Program Workshop Atlanta, Georgia, February 5, 2004 This work was performed.

Chapter 1. Essential Concepts

NEEP 541 Molecular Dynamics Fall 2002 Jake Blanchard.

Liquid Walls Town Meeting May 5, 2003, Livermore, CA Work performed under the auspices of the U. S. Department of Energy by University of California Lawrence.

Progress Report on SPARTAN Chamber Dynamics Simulation Code Farrokh Najmabadi, Zoran Dragojlovic HAPL Meeting April 8-10, 2003 Sandia National Laboratory,

Modeling of Z-Ablation I. E. Golovkin, R. R. Peterson, D. A. Haynes University of Wisconsin-Madison G. Rochau Sandia National Laboratories Presented at.

S.I. Golubov, S.J. Zinkle and R.E. Stoller

RADIATION EFFECTS OF COPPER SINGLE CRYSTALS UNDER STRESS

Tungsten Armor Engineering:

Jeff Latkowski and Wayne Meier

Presentation transcript:

LLNL Chambers Activities Presented by: Jeff Latkowski Chambers Team: Ryan Abbott, Alison Kubota, Wayne Meier, Susana Reyes April 10, 2003 Work performed under the auspices of the U. S. Department of Energy by Lawrence Livermore National Laboratory under Contract W-7405-Eng-48.

LLNL chambers work spans three areas Chamber and systems design Safety & environmental analyses Molecular dynamics simulations

Chamber scaling work will eventually be part of a Laser IFE systems code Eventual goal is an integrated systems model of an IFE power plant to help select attractive point design(s) Focus this year is on scaling relationships for a dry-wall chamber Approach is to use simple scaling tied to results from more detailed calculations

Many constraints need to be considered in the chamber/blanket design Tungsten armor on ferritic steel wall/blanket Peak W temp < Tmelt Peak Fe temp < Max allowable operating temp Pulse to pulse  T at W/Fe interface < ? interface integrity constraint? Thermal stresses due to avg  T across steel wall Cylic stresses due to neutron induced pressure pulse in first wall coolant Surface roughing due to ion implantation Neutron damage Others?

Example: Scaling maximum surface temperature of W armor 1D temperature for surface heat flux qo applied starting at t = 0. k = thermal conductivity,  thermal  diffusivity, To = initial temperature  At the surface  Heat flux: fxd = x-ray and debris fraction, Y = target yield, Rw = wall radius,  p = pulse length Since  p ~ 1/Rw, Tmax ~ To + Y/Rw 2.5 Assuming T max occurs at t ~  p  Surface temp at t =  p

Simple scaling compares favorably to Blanchard’s results 50  m W, No gas, Y = 154 MJ, To ~ 500C Tmelt Blanchard pts Scaling eqn. Next steps: - Add effect of gas fill - Need more calcs at various yields - Scaling parameters important to other constraints

Molecular dynamics simulations of radiation damage in tungsten chamber materials During the first year, we will use MDS to evaluate defect production as a function of recoil energy (several to tens of eV) MDS involves the numerical time-integration of Newton’s equation of motion for an ensemble of N -interacting particles (atoms), F i = m i a i = -  V(r 1,r 2,…, r N ) Given an interatomic potential. We have available, the Embedded Atom Method (EAM) potentials of Finnis-Sinclair and Ackland, V(r 1,r 2,…, r N ) = V R + V E Where V R is a repulsive pairwise contribution, and V E is the embedding energy of an atom in an electron gas, with the form, V E (  i ) = (∑ ij  (r ij )) 1/2 Where  (r ij ) are the individual neighbor contributions to the embedding electron density

Previous MDS studies in tungsten Li and Shi, Study of dislocation Motion, EAM (Finnis-Sinclair) potentials Mundim, et al., Energetics of defect migration, Morse Potential fit to electronic structure data Komandri, Chandrasekaran and Raff, Study of atomic-scale friction Morse Potentials Zhong, Nordlund, Ghaly and Averback, Defect production near free-surfaces, keV recoils, EAM (Finnis-Sinclair) potentials Grujicic, Zhao and Krasko, Grain boundary fracture, EAM (Finnis-Sinclair) potentials Kinney and Guinan, Defect production near surfaces, Morse Potentials

Analyses: Voronoi cell analysis to calculate defects The Voronoi cell associated with a single atom is the constructed polyhedral volume for which all points contained within the volume are nearest to the associated atom. Voronoi Cell for FCC LatticesVoronoi Cell for BCC Lattices Zero-occupancy denote a vacancy Double-occupancy denotes an interstitial

Example: 2 keV recoil in FCC metal 0.76 psec 2.76 psec4.76 psec 6.76 psec 8.76 psec18.76 psec White = Interstitial (Dumb-bell)Magenta = Vacancy

Activation cross sections may need to be improved for IFE safety assessments Previous work has identified isotopes and reactions that are critical for safety & environmental issues Preliminary results show that uncertainties in activation cross sections could be significant Two methods have been implemented in the ACAB code: –a comprehensive sensitivity-uncertainty analysis method –a Monte Carlo procedure based on simultaneous random sampling of all the cross sections involved in the problem We will determine if any of the uncertainties are large enough to have an impact upon any of our key results and/or conclusions

Activation calculations have been completed for three FW/blanket concepts 1.Original SOMBRERO concept with 1 cm C/C first wall and C/C blanket 2.W-3Re armor (1 mm) with SiC first wall and blanket 3.W-3Re armor (1 mm) with ferritic steel first wall and blanket

Waste disposal ratings have been calculated for each armor/wall/blanket option Results assume 1 yr irradiation time W-3Re components would not meet Class C disposal requirements unless exposed for <2 years (dominated by Re, which is added for ductility) Ferritic steel WDR dominated by Nb, Mo impurities (0.5, 70 wppm, respectively) WDR C/CW-3Re/SiC W-3Re/ ferritic steel armor N/A5.4E-015.3E-01 first wall 7.5E-046.2E-033.9E-01 blanket structures 9.7E-051.1E-045.9E-02

Waste disposal ratings have been calculated for each armor/wall/blanket option Results assume 1 yr irradiation time W-3Re components would not meet Class C disposal requirements unless exposed for <2 years (dominated by Re, which is added for ductility) Ferritic steel WDR dominated by Nb, Mo impurities (0.5, 70 wppm, respectively) WDR C/CW-3Re/SiC W-3Re/ ferritic steel armor N/A5.4E-015.3E-01 first wall 7.5E-046.2E-033.9E-01 blanket structures 9.7E-051.1E-045.9E-02 Similar analyses needed as function of Re content, impurities, chamber radius, etc.

MDS Parallelization by Spatial Decomposition mcr13mcr14mcr15mcr16 mcr29mcr30mcr31mcr32 mcr45mcr46mcr47mcr48 mcr61mcr62mcr63mcr64 Data Environment Hardware An Array of Link Cells Link-Cell Decomposition Spatial Decomposition Link-Cell Sizes are based on cutoff- lengths (4.4A for W)

Questions for Alison: 1 st slide/1 st bullet: really several to tens of eV (vs. keV)? How/where do we work in experimental validation? Have copy of walkthrough description? (Download this) Worth going through method of parallelization?