Simulating fusion neutron damage using protons in ODS steels Jack Haley.

Slides:



Advertisements
Similar presentations
PWI Modelling Meeting – EFDA C. J. OrtizCulham, Sept. 7 th - 8 th, /8 Defect formation and evolution in W under irradiation Christophe J. Ortiz Laboratorio.
Advertisements

Chapter 22 – Nuclear Chemistry
CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority Culham Materials Research Facility - for universities, industry and fusion.
Investigation of Proton Irradiation-Induced Creep of Ultrafine Grain Graphite Anne A. Campbell & Gary S. Was University of Michigan Research Supported.
Irradiation study of Ti-6Al-4V and Ti-6Al-4V-1B for FRIB beam dump: Experimental plan Aida Amroussia, PhD Student Chemical Engineering and Materials Science.
Study of Thermal Properties of Irradiation-induced Stainless Steels Used in the Development of Nuclear Reactors Mauricio Londono, Mechanical and Energy.
RaDIATE 1 st Annual Collaboration Meeting May Cost-effective Irradiations Discussion Radiation Damage In Accelerator Target Environments.
Nuclear Chemistry Bravo – 15,000 kilotons. CA Standards.
Structural response of SiC and PyC on swift heavy ion irradiation
An In-situ TEM Investigation of Silicon Carbide under Irradiation Chris Pawley University of Salford UNTF 2011, April 2011, University of Huddersfield.
1 Fundamentals of Void Swelling in Metal Alloys L. K. Mansur Workshop on Characterization of Advanced Materials under Extreme Environments for Next Generation.
Accelerator technique FYSN 430 Fall Syllabus Task: determine all possible parameters for a new accelerator project Known: Scope of physics done.
Materials for fusion power plants Stéphane Forsik - Phase Transformations and Complex Properties Group FUSION POWER PLANT.
Atom Probe Tomography of Ion- Irradiated Model ODS Alloys Andrew London* 4 th Year DPhil C.R.M Grovenor, S Lozano-Perez* B. K. Panigrahi** * Department.
Oct.18, Neutron Field and Induced Radioactivity in IFMIF Environment M. Sugimoto(JAERI) IEA International Work Shop on Fusion Neutronics The Kongreshous.
FETS-HIPSTER (Front End Test Stand – High Intensity Proton Source for Testing Effects of Radiation) Proposal for a new high-intensity proton irradiation.
Developing a Vendor Base for Fusion Commercialization Stan Milora, Director Fusion Energy Division Virtual Laboratory of Technology Martin Peng Fusion.
Martin Freer Materials Irradiation at University of Birmingham.
Measurement and modeling of hydrogenic retention in molybdenum with the DIONISOS experiment G.M. Wright University of Wisconsin-Madison, FOM – Institute.
NEEP 541 Radiation Interactions Fall 2003 Jake Blanchard.
“Influence of atomic displacement rate on radiation-induced ageing of power reactor components” Ulyanovsk, 3 -7 October 2005 Displacement rates and primary.
PASI Workshop, Fermilab Jan Radiation Damage and Radio-chemistry Issues N. Simos, H. Kirk, BNL P. Hurh, N. Mokhov, FNAL K. McDonald, Princeton.
Overview of ‘classical’ or ‘standardized’ DPA calculation stemming from the reactor world. Colin English NNL.
IRRADIATION EXPERIMENTS & FACILITIES AT BNL: BLIP & NSLS II Peter Wanderer Superconducting Magnet Division, BNL WAMSDO – November 14, 2011.
1 1) Japan Atomic Energy research Institute 2) Institute of Advanced Energy, Kyoto University 3) Japan Nuclear Cycle Development Institute Progress of.
ISIS Target studies Could a used ISIS target provide fusion relevant irradiated tungsten material properties? Tristan Davenne 20 th May nd Radiate.
THE NUCLEUS: A CHEMIST’S VIEW. Nuclear Symbols Element symbol Mass number, A (p + + n o ) Atomic number, Z (number of p + )
Positron and Positronium Chemistry PPC10, September, Smolenice Castle, Slovakia Thermal annealing influence on ions implanted Fe-Cr model alloys.
NEEP 541 – Radiation Damage in Steels Fall 2002 Jake Blanchard.
This work was performed under the auspices of the U.S. Department of Energy by University of California Lawrence Livermore National Laboratory under Contract.
MATERIAL ISSUES FOR ADS: MYRRHA-PROJECT A. Almazouzi SCKCEN, Mol (Belgium) On behalf of MYRRHA-TEAM and MYRRHA-Support.
FAST NEUTRON IRRADIATION-INDUCED DAMAGE ON GRAPHITE AND ZIRCALOY- 4 TSHEPO MAHAFA University of Johannesburg Supervisor: Dr Emanuela Carleschi (UJ) Co-Supervisor:
Proposal for uranium micro-beam linac at the APS for reactor fuel and structural materials studies 1 MeV/u heavy ions up to uranium includes “fission fragments”
“Materials for Fission & Fusion Power” Steve Roberts Sergei Dudarev CCFE George Smith Gordon Tatlock Liverpool Angus Wilkinson Patrick Grant Andrew Jones.
FETS*-HIPSTER** * Front End Test Stand **High Intensity Proton Source for Testing Effects of Radiation Chris Densham, Tristan Davenne, Alan Letchford (RAL),
The Materials Test Station: An Accelerator Driven Neutron Source for Fusion Materials Testing Eric Pitcher Presented at: Sixth US-PRC Magnetic Fusion Collaboration.
The use of both neutron and ion irradiation to show the microstructural origins of strong flux-sensitivity of void swelling in model Fe-Cr-Ni alloys T.
VIEW on RAD HARDNESS TESTS of STS FEE IN MEPHI. Simakov A.B. – Head of “Special Microelectronics” Lab.
PROGRESS ON LOW ACTIVATION STRUCTURAL STEELS RECENT RESULTS ON NANOSTRUCTURED FERRITIC ALLOYS A.F.ROWCLIFFE (ORNL) ARIES PROJECT MEETING U.C.S.D. Jan 22.
1 Russian Research Center” Kurchatov Institute” Alexander Ryazanov Charge State Effects of Radiation Damage on Microstructure Evolution in Dielectric Materials.
Nuclear Physics.
Applications of Demokritos TANDEM Accelerator in Fusion Technology Research TANDEM Lab I.N.P.P M. Andrianis S. Harisopoulos A. Lagoyianis G. Provatas National.
Open Access and Free Journals In OutLook OnLine: A Demonstration
10th ITPA conference, Avila, 7-10 Jan Changes of Deuterium Retention Properties on Metals due to the Helium Irradiation or Impurity Deposition M.Tokitani.
1 Clip. 1. Differentiate among alpha and beta particles and gamma radiation. 2. Differentiate between fission and fusion. 3. Explain the process half-life.
G.I. SmirnovMaterials for Collimators and Beam Absorbers, Simulating radiation damage effects in LHC collimators (code development status)
1 SPIRE Project coordinated by CEA – Contractors : CEA, CIEMAT, CNRS, NRG, ENEA, PSI, KTH, SCK/CEN, FZK « IRRADIATION EFFECTS IN MARTENSITIC STEELS UNDER.
NEEP 541 – Neutron Damage Fall 2002 Jake Blanchard.
Radiation Damage Quick Study Edward Cazalas 3/27/13.
NEEP 541 – Phase Transformation due to Radiation Fall 2003 Jake Blanchard.
FETS-HIPSTER A High-Flux Proton Irradiation Facility Steve Roberts (University of Oxford) Chris Densham (RAL), Alan Letchford (RAL), Juergen Pozimski (Imperial.
SIC FIBERS MECHANICAL AND MICROSTRUCTURAL BEHAVIOR UNDER ION IRRADIATION TUTORS: J.M. COSTANTINI / A. JANKOWIAK / S. MIRO Juan HUGUET-GARCIA 1rst year.
4.1.1 Nanostructure and micro chemical evolution under irradiation and thermal ageing g : development of phase field models describing microstructure.
In situ and postradiation analysis of mechanical stress in alumina under swift heavy ion irradiation V.A.Skuratov 1, G.Bujnarowski 1,2, Yu.S.Kovalev 1,
Characterization of He implanted Eurofer97
Alloy Design For A Fusion Power Plant
Reminder of few basic facts about displacements per atom (dpa)
Fernando Mota, Christophe J. Ortiz, Rafael Vila
Australian Nuclear Science and Technology Organisation, Australia
Ming Tang, Los Alamos National Laboratory, USA Eric R. Vance,
Iuliia Ipatova; Evolution of the lattice defects in Tantalum-Tungsten alloys under irradiation Iuliia Ipatova;
Outside the nucleus, the beta decay {image} will not occur because the neutron and electron have more total mass than the proton. This process can occur.
Russian Research Center “ Kurchatov Institute”
Nuclear Chemistry Bravo – 15,000 kilotons.
AKA Radioactive DECAY or NUCLEAR DECAY
AKA Radioactive DECAY or NUCLEAR DECAY
THE NUCLEUS: A CHEMIST’S VIEW
Three kinds of particle emission
XI Reactor Material Science Conference, Dimitrovgrad,
Presentation transcript:

Simulating fusion neutron damage using protons in ODS steels Jack Haley

1.Fusion Power and radiation damage 2.Simulating neutron damage 3.Simulating with protons 4.Project plan

Fusion Power Deuterium and Tritium fuse to produce a 3.5MeV alpha particle and 14.1MeV neutron

Neutrons cause hardening, embrittlement and swelling in components. Enormous demands placed on the structural steels ODS steels are excellent at handling the radiation ODS precipitates pin dislocations and act as sinks for defects and Helium [1] Fusion Power [1] Brodrick, J., Hepburn, D. J., & Ackland, G. J. (2014). Mechanism for radiation damage resistance in yttrium oxide dispersion strengthened steels. Journal of Nuclear Materials, 445(1-3), 291–297. doi: /j.jnucmat

Simulating the neutrons Closest thing to fusion neutrons available fission neutrons Lower energy (~2MeV) Takes a long time Makes samples radioactive Self ion irradiation is widely used High dose rate Many facilities available, eg JANNUS, MIAMI Multi beam energies In situ with TEM, Helium implantation Self ions irradiation behave like the primary knock on atom in neutron irradiation Fission neutron PKA up to 200keV Fusion neutron PKA up to 1MeV [2] [2] Dierckx, R. (1987). The importance of the pka-energy for damage simulation spectrum. Journal of Nuclear Materials, 144, 214–

Simulating with self-ions

[3] Taken from Chris Hardie’s Dphil thesis, 2012 Oxford University

Simulating with self-ions Size effect in micromechanical testing As sample size decreases, yield strength increases [3] Taken from Chris Hardie’s Dphil thesis, 2012 Oxford University Fe-6Cr [3]

Simulating with protons

Higher dose rate than neutrons, but much lower than heavy ions – need higher currents Very different recoil energy (PKA <0.5keV) than fusion neutrons

Simulating with protons Dominant energy loss mechanism of proton is by ionization May be a problem with ODS steels – oxide precipitates could be degraded due to the ionization

Gary Was et al – Emulation of neutron irradiation effects with protons: Validation of principle [4] 2002 paper studied:  Radiation Induced Segregation  Microstructure (dislocation loops)  Irradiation hardening  Susceptibility to IASCC Found excellent agreement between fission neutrons irradiated at 275 o C and 3.2MeV protons at 360 o C Higher temperature proton irradiation balances the increased displacement rate by enhancing diffusion kinetics. [4] Was, G. S. et. Al. (2002). Emulation of neutron irradiation effects with protons : validation of principle, 300, 198–216. Protons in the literature

Still no proton studies on martensitic FeCr and ODS steel Recoil energy influence on the radiation induced damage is dependent on  Composition  Irradiation temperature  Lattice structure There is no magic formula (yet!) for determining appropriate proton irradiation conditions to reliably mimic neutron damage Simulating with protons

University of Birmingham has two particle accelerators available for proton irradiation of materials Simulating with protons Accelerator facilities are housed in the Medical Physics Building at the University Image Copyright Phil Champion. This work is licensed under the Creative Commons Attribution-Share Alike 2.0 Generic Licence. To view a copy of this licence, visit or send a letter to Creative Commons, 171 Second Street, Suite 300, San Francisco, California, 94105, USA.  Cyclotron 1-9MeV protons – 2.9MeV preferred set up ~10μA beam current up to 2cm diameter beam size Capable of ~10 -6 dpa/s in Iron which translates as ~0.05 dpa/day Temperature control up to 600 o C available now  Dynamitron 1-3MeV protons 100s of μA beam current easily possible, absolute maximum 2mA Up to 2cm diameter beam size ~ dpa/s ~1 dpa/day at 100 μA Temperature control in the works

Project plan Key questions: How is the microstructural damage produced by proton, heavy ion and fission neutrons different? What are the differences in mechanical properties? Is the proton damage representative of neutron damage under any irradiation conditions?

Project plan Next Steps Start work initially on FeCr binary alloys 0-15% Cr content ODS steels later Heavy ion irradiation at JANNUS in May Use Cyclotron in the summer for first proton irradiations, up to 0.6dpa to match neutron specimens at CCFE at same temperature Once Dynamitron is ready, use to irradiate at higher doses

Project plan Characterise the microstructural damage using TEM and relate this with micromechanical tests  Dislocation loops  Hardening using nano-indentation and micro-cantilevers  Atom probe tomography? Dose and dose rate dependance Irradiation temperature dependence Composition dependence