PASI Workshop, Fermilab Jan 12-13 2012 Radiation Damage and Radio-chemistry Issues N. Simos, H. Kirk, BNL P. Hurh, N. Mokhov, FNAL K. McDonald, Princeton.

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Presentation transcript:

PASI Workshop, Fermilab Jan Radiation Damage and Radio-chemistry Issues N. Simos, H. Kirk, BNL P. Hurh, N. Mokhov, FNAL K. McDonald, Princeton U R. Bennett, RAL

PASI Workshop, Fermilab, Jan Parameter Space (damage is missing !!!)

PASI Workshop, Fermilab, Jan Motivation: Need for multi-MW level operations and beams associated with proposed long baseline neutrino experiments (i.e. LBNE) Yield of useful pions/parents of the neutrinos of interest from low-Z materials is well matched to requirements of most neutrino experiments Peak energy deposition in low-Z targets is lowest; Graphite shown to exhibit superior thermo- mechanical performance confirmed by experience data from nuclear reactors Identification of limitations (if any) of low- Z materials under intense proton beams in support of MW-level experiments Background – Irradiation Damage & Accelerators Extrapolation of nuclear reactor experience data on radiation damage extremely risky Elastic collisions (transferring of recoil energy to a lattice atom) leading to displaced atoms (dpa) Inelastic collisions  transmutation products (H, He) Series of experiments at BNL using the 200 MeV Linac on materials, some with excellent performance in reactors (tens of dpa damage) showed presence of proton fluence threshold (~10^21 p/cm2) (LHC beam collimation studies at BNL first revealed shortcomings of carbon based materials) realization For multi-MW level experiments, i.e. LBNE, apparent threshold COULD be a limiting factor Threshold is within year of operation at LBNE

PASI Workshop, Fermilab, Jan Radiation effects on materials  Understand effects of irradiating species  Energy  Rate  Operating Environment

PASI Workshop, Fermilab, Jan The Radiation Damage Problem Simplified  Material properties change significantly as they are irradiated due to microstructural disorder  Design limits vary with exposure  In general: Strength increases Ductility decreases Thermal/Electrical conductivity decreases  Not only targets, but also windows, collimators, instrumentation, etc…  Data for LE neutron irradiation is relatively plentiful, not so for HE proton irradiation

PASI Workshop, Fermilab, Jan The Radiation Damage Problem - Complicated  Critical Mat’l properties sensitive to radiation damage include (note difference between LE neutron and HE proton): Irradiation particle, e.g. protons vs. neutrons Particle energy Flux or dose rate (dpa/s) Fluence or dose (dpa) Irradiation temperature Transmutation (e.g. He, H) Pulsed irradiation vs. continuous irradiation These constitute “damage correlation parameters” Use these parameters to correlate damage from LE neutron to HE proton irradiation? – Could be powerful to harness the data from reactors for use in proton accelerator target facility designs

PASI Workshop, Fermilab, Jan The Radiation Damage Problem Complicated  Material property changes are sensitive to many parameters (not captured by DPA): Tensile and yield strengths Modulus of Elasticity Coef. of Thermal Expansion Heat Capacity Electrical and Thermal Conductivity Density/Dimensions (Swelling) Fracture Toughness Fatigue Strength Irradiation creep Hydrogen/Helium Embrittlement Sonic velocity Corrosion resistance “Threshold” of significant property change is material dependent – 0.02 DPA for graphite – 1-10 DPA for stainless steel

PASI Workshop, Fermilab, Jan Annealing or defect mobility at elevated temperature Irradiation damage & Reversal  how does it manifest its self both in micro- and macro-scales?  irreversible ? Observed Behavior: Increased defect density, damage acceleration upon re-exposure Why and what is the responsible mechanism? Does it apply with all alloys?

PASI Workshop, Fermilab, Jan Radiation Accelerated Corrosion  Ionization of air surrounding a target by primary and secondary particles can create a very aggressive, corrosive environment  High strength steel may suffer hydrogen embrittlement (MiniBooNE, NuMI)  Coupled with radiation damage of material, not only accelerates corrosion, but changes the nature of the corrosion morphology (localized pitting versus uniform layer; NuMI decay pipe window)

PASI Workshop, Fermilab, Jan Radiation Accelerated Corrosion  Al 6061 samples displayed significant localized corrosion after 3,600 Mrad exposure  NuMI target chase air handling condensate with pH of 2  NuMI decay pipe window concerns R.L. Sindelar, et al., Materials Characterization 43: (1999). 3/30/11 10 P. Hurh: High-Power Targets: Experience and R&D for 2 MW

PASI Workshop, Fermilab, Jan Radiation Accelerated Corrosion  Photograph of NuMI decay pipe US window showing corroded spot corresponding to beam spot 3/30/11 11 P. Hurh: High-Power Targets: Experience and R&D for 2 MW

PASI Workshop, Fermilab, Jan Any High Power Integrated Target System will be subjected to all that

PASI Workshop, Fermilab, Jan Use of BNL Accelerator Complex for Material Damage  Direct protons ( MeV) on materials  Spallation neutrons, gammas, electrons and secondary protons (isotope targets serving as spallation targets – 2011 beam run) TargetE p (GeV) Beam  (mm) N p (1/yr)DPA (1/yr) NuMI/LBNE e BLIP e221.5 Why radiation damage at BLIP?

PASI Workshop, Fermilab, Jan Graphite & Carbon Composites

PASI Workshop, Fermilab, Jan Graphite and C-C (Maruyama and Harayama 1992) (Snead 2009)

PASI Workshop, Fermilab, Jan Neutron irradiation of polygranular graphite (shrinkage at low doses and expansion at high doses.(Kasten et al 1969).

PASI Workshop, Fermilab, Jan Low-Z Targets and LBNE Graphite and Carbon-fiber composites Graphite widely studied and used in reactors Its behavior, however, remains elusive

PASI Workshop, Fermilab, Jan p/cm 2 fluence  0.2 dpa what happened to the 10s of dpa seen in thermal reactors? Observations were reproduced 3 times !!

PASI Workshop, Fermilab, Jan Graphite and carbon composites under high proton fluences BNL target studies to 10^21 p/cm2 (NuMI, J. Hylen)

PASI Workshop, Fermilab, Jan LBNE Target Experiment at BNL Linear Isotope Producer (BLIP) Experiment Objectives: Establish relation between limiting fluence threshold and operating environment Confirm damage & energy dependence (120 GeV vs. 180 MeV) Identify the optimal low-Z microstructure when exposed to similar fluence/temp/environment conditions Select the baseline target from material performance during LBNE test TargetE p (GeV) Beam  (mm) N p (1/yr)DPA (1/yr) NuMI/LBNE e BLIP e MW LBNE can be achieved at BNL BLIP over ~7 weeks MARS Analysis Material damage dependency on proton energy and irradiation rate LBNE/NuMI & BNL BLIP Equivalence NuMI “segmented” graphite target BNL BLIP Target Configuration LBNE Target Array

PASI Workshop, Fermilab, Jan What have LBNE Radiation Damage Experiments have shown:

PASI Workshop, Fermilab, Jan

Super Alloys

PASI Workshop, Fermilab, Jan super-Invar

PASI Workshop, Fermilab, Jan

annealing following neutron irradiation

PASI Workshop, Fermilab, Jan Ti-12Ta-9Nb-3V-6Zr-O [“gum” metal] T. Saito, et al., Multifunctional Alloys Obtained via a Dislocation-Free Plastic Deformation Mechanism, Science, 300 (2003) 464

PASI Workshop, Fermilab, Jan From super-ductile to TOTALLY brittle ! WHY is it so susceptible? * bombardment of this “unstable” equilibrium * He formed & retained in grain boundaries Radiation effects on Mechanical Properties of Gum Metal

PASI Workshop, Fermilab, Jan Unique gum metal linear expansion behavior

PASI Workshop, Fermilab, Jan Irradiated Gum Metal

PASI Workshop, Fermilab, Jan Characterization using Photon Spectra

PASI Workshop, Fermilab, Jan Characterization using Photon Spectra

PASI Workshop, Fermilab, Jan

Ti-6Al-4V

PASI Workshop, Fermilab, Jan High-Z Materials and Irradiation

PASI Workshop, Fermilab, Jan Accelerated Ta Oxidation: Present of a third element Radiation-induced oxidation acceleration ? Experimental Set-Up addressing Oxidation/Volumetric Change (i.e. tantalum) 1200 deg. C 625 deg. C 20 deg. C

PASI Workshop, Fermilab, Jan Dose increase Work hardening dislocations in motion

PASI Workshop, Fermilab, Jan

2 dpa (70% mass loss)

PASI Workshop, Fermilab, Jan Irradiation, temperature and corrosive environment on Ni film with AL substrate After irradiation Before irradiation Ni on aluminum: Magnetic Horn (NuMI Experiment) This may not occur in the absence of irradiation (or not as fast !)

PASI Workshop, Fermilab, Jan Way Forward

PASI Workshop, Fermilab, Jan Radiation Damage R&D Opportunities  Further irradiation and testing of promising target materials and "super" materials Requires beam time, hot cell work & Material Science expertise  Correlate LE neutron irradiation data to HE proton regime to take advantage of neutron irradiation data Requires Material Science expertise & access to data  Study effects of gas production in solid and liquid target materials Requires Material Science, Radiochemistry, and Simulation expertise May require testing

PASI Workshop, Fermilab, Jan Radiation Damage R&D Opportunities  Irradiation tests to validate DPA and gas production simulation tools Requires Material Science and Simulation expertise Requires beam time & hot cell work  Participate in activities to characterize irradiated materials from operating facilities (such as the SNS target vessel testing) Requires Mechanical Engineering, Material Science expertise

PASI Workshop, Fermilab, Jan Radiation Damage R&D Opportunities  Develop white paper outlining parameter space required for an irradiation test facility Requires ME, Mat’l Science, Accelerator Physicist, and Simulation expertise  Develop proposals for non-parasitic irradiation test sites at operating facilities (NuMI hadron absorber?) Requires ME, Mat’l Science, Accelerator Physicist, and Simulation expertise

PASI Workshop, Fermilab, Jan To provide a test bed for:  material irradiation under protons and neutrons (thermal and fast)  Neutron scattering and damage assessment Unique Features Proton Energy Optimization and Selectivity for target material damage (FFAG and coupled cavities are explored) Selectivity of neutron spectra for material damage Neutron scattering for micro-scale damage evaluation BLAIRR The Brookhaven Linear Accelerator IRRadiation Test Facility

PASI Workshop, Fermilab, Jan Present Parameter Space MeV Proton Beam 105 μA Beam Sigma Spallation neutron spectrum from 112 MeV Protons Sharing Target Irradiation R Activities Material irradiation damage by proton irradiation Spallation neutron material irradiation Future Dedicated Target Space customized/optimized Synchronous proton and neutron irradiation damage Utilization of Spatial properties of spallation neutron spectrum Tunable proton energy to several hundred MeV (optimized according to the primary target and the neutron spectra desired) MOST importantly use spallation neutrons for neutron scattering studies of irradiation damage Brookhaven Linear Accelerator IRRadiation Test Facility N. Mokhov

PASI Workshop, Fermilab, Jan BLAIRR – A Unique, ALL IN ONE OPERATION High Rate Irradiation Damage from Energetic Protons Fast Neutron Irradiation or Fast and Fusion Reactor Materials Crystal and Special Detector Performance Degradation Neutron Scattering based Damage Assessment Macroscopic Damage Assessment Computational Damage Model Verification

PASI Workshop, Fermilab, Jan Molecular Dynamics and Damage Evolution Fragment track and thermal spike on the surface of fused silica bombarded with energetic particles CZT crystal

PASI Workshop, Fermilab, Jan o Molecular Dynamics o Monte-Carlo analysis Visualization of damage (X-ray probing/strain mapping) Light Source Re-engineering of nano- /micro-structure at CFN Envisioned Synergistic Model Irradiation & macroscopic assessment