FAST NEUTRON IRRADIATION-INDUCED DAMAGE ON GRAPHITE AND ZIRCALOY- 4 TSHEPO MAHAFA University of Johannesburg Supervisor: Dr Emanuela Carleschi (UJ) Co-Supervisor:

Slides:



Advertisements
Similar presentations
Investigation of Proton Irradiation-Induced Creep of Ultrafine Grain Graphite Anne A. Campbell & Gary S. Was University of Michigan Research Supported.
Advertisements

Study of Thermal Properties of Irradiation-induced Stainless Steels Used in the Development of Nuclear Reactors Mauricio Londono, Mechanical and Energy.
Atomic Scale Modelling of Zirconium Alloys and Hydrogen in Zirconium By Simon Lumley Supervised by Dr Mark Wenman, Prof. Robin Grimes and Dr Paul Chard-Tuckey.
RUSSIAN RESEARCH CENTER KURCHATOV INSTITUTE Development of annealing for VVER-1000 reactor vessels Experimental assessment of possibility for performance.
NEEP 541 – Defects Fall 2003 Jake Blanchard. Outline Irradiation Induced Defects Definitions Particles Cascades Depleted zones Thermal Spikes.
Structural response of SiC and PyC on swift heavy ion irradiation
Charged Particle Radiation
1 Fundamentals of Void Swelling in Metal Alloys L. K. Mansur Workshop on Characterization of Advanced Materials under Extreme Environments for Next Generation.
Materials for fusion power plants Stéphane Forsik - Phase Transformations and Complex Properties Group FUSION POWER PLANT.
VG.1 SCWR Fuel Rod Design Requirements Design Limits Input for Performance Evaluations H. Garkisch, Westinghouse Electric Co.
Adam Smalley.  Describe how neutrons produced in a fission reaction may be used to initiate further fission reactions (chain reactions)  Distinguish.
A.V. Kozlov, I.A. Portnykh, V.L. Panchenko FSUE «INM», , Box 29, Zarechny, Sverdlovsk region, Russia Corresponding author. fax: ;
Influence of neutron irradiation parameters on swelling and mechanical properties of stainless steels - materials of BN-350 fuel assembly ducts O.P.Maksimkin,
FETS-HIPSTER (Front End Test Stand – High Intensity Proton Source for Testing Effects of Radiation) Proposal for a new high-intensity proton irradiation.
1 A.I.Ryazanov, E.V.Semenov and A.Ferrari DPA calculations in irradiated graphite collimator materials under 7 TeV and 450 GeV proton beams ,
OVERVIEW Material Irradiation Damage Studies at BNL BLIP N. Simos and H. Kirk, BNL K. McDonald, Princeton U N. Mokhov, FNAL (Oct. 20, 2009) (BLIP = Brookhaven.
Examination and Improvement of SHEM multigroup energy structure Tholakele P. Ngeleka Radiation and Reactor Theory, Necsa, RSA Ivanov Kostadin, Levine Samuel.
Overview of ‘classical’ or ‘standardized’ DPA calculation stemming from the reactor world. Colin English NNL.
Breazeale Nuclear Reactor Penn State Radiation Science and Engineering Center.
1 1) Japan Atomic Energy research Institute 2) Institute of Advanced Energy, Kyoto University 3) Japan Nuclear Cycle Development Institute Progress of.
EuCARD-2 is co-funded by the partners and the European Commission under Capacities 7th Framework Programme, Grant Agreement EuCARD 2 ColMat-HDED.
Distributions of fission products on PCI in spent PWR fuels using EPMA
JP Nuclear Materials Sub-programme 4 - Physical modelling and modelling-oriented experiments on structural materials The Joint Programme for Nuclear Materials.
Andrea Salvini, CERN, L.E.N.A. Laboratory at Pavia University (Laboratorio Energia Nucleare Applicata) TRIGA Mark II pool research reactor.
Simulating fusion neutron damage using protons in ODS steels Jack Haley.
NE Introduction to Nuclear Science Spring 2012 Classroom Session 7: Radiation Interaction with Matter.
Tshepo Mahafa P-LABS Necsa 1 CHARGED PARTICLE IRRADIATION EFFECTS ON ZIRCALOY-4 Necsa_Wits Workshop, 10 – 11 September 2015, Necsa, Pelindaba.
Irradiation Effects in Graphite – from the Nano- to the Mille- Metric Scale Tim Burchell Distinguished R & D Staff Member Fusion Materials & Nuclear Structures.
NEEP 541 – Radiation Damage in Steels Fall 2002 Jake Blanchard.
NEEP 541 – Material Properties Fall 2003 Jake Blanchard.
MATERIAL ISSUES FOR ADS: MYRRHA-PROJECT A. Almazouzi SCKCEN, Mol (Belgium) On behalf of MYRRHA-TEAM and MYRRHA-Support.
Hydride Induced Embrittlement on Zircaloy-4
ORNL is managed by UT-Battelle for the US Department of Energy Annealing Studies of Irradiated HOPG using X-ray Measurements Nidia C. Gallego Melanie J.
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.
Nuclear Safety Research Unit Vienna (Austria), IAEA meeting Evaluation of creep during dry storage in low and high burnup fuels F. Feria,
DAVID VAN WAGENER NOVEMBER 26, 2008 CHE 384: TECHNOLOGY REPORT Nuclear Power: Advanced Generations and Outlook.
Nuclear Chemistry Part II “The discovery of nuclear reactions need not bring about the destruction of mankind any more than the discovery of matches” -Albert.
4/2003 Rev 2 I.4.9h – slide 1 of 24 Session I.4.9h Part I Review of Fundamentals Module 4Sources of Radiation Session 9hFuel Cycle – Spent Fuel IAEA Post.
Applications of Demokritos TANDEM Accelerator in Fusion Technology Research TANDEM Lab I.N.P.P M. Andrianis S. Harisopoulos A. Lagoyianis G. Provatas National.
In your notes… What are the four ways we harness solar energy? What are the limitations of solar energy (at least 2)? What approach should we take with.
1 Segrè Lost … ! Nuclear Fission How much is recoverable? How much is recoverable? What about capture gammas? (produced by -1 neutrons) What about capture.
1 SPIRE Project coordinated by CEA – Contractors : CEA, CIEMAT, CNRS, NRG, ENEA, PSI, KTH, SCK/CEN, FZK « IRRADIATION EFFECTS IN MARTENSITIC STEELS UNDER.
Radiation Damage Quick Study Edward Cazalas 3/27/13.
Sources of Radiation Research Reactors
Investigation of 15kh2NMFAA steel and weld after irradiation in the “Korpus” facility on the RBT-6 reactor D. Kozlov, V. Golovanov, V. Raetsky, G. Shevlyakov,
The effect of radiation damage by fission fragments on dissolution of spent nuclear fuel Aleksej Popel, PhD candidate Supervisor: Dr Ian Farnan Department.
Nuclear Power Plant How A Nuclear Reactor Works. Pressurized Water Reactor - Nuclear Power Plant.
FETS-HIPSTER A High-Flux Proton Irradiation Facility Steve Roberts (University of Oxford) Chris Densham (RAL), Alan Letchford (RAL), Juergen Pozimski (Imperial.
MEASURING RADIATION Large doses of radiation are harmful to living tissue. Radiation can be measured with a Geiger counter – a device that measures radioactivity.
SIC FIBERS MECHANICAL AND MICROSTRUCTURAL BEHAVIOR UNDER ION IRRADIATION TUTORS: J.M. COSTANTINI / A. JANKOWIAK / S. MIRO Juan HUGUET-GARCIA 1rst year.
Investigation of the Performance of Different Types of Zirconium Microstructures under Extreme Irradiation Conditions E.M. Acosta, O. El-Atwani Center.
LOW PRESSURE REACTORS. Muhammad Umair Bukhari
Summary HiLuMI LHC Collimation Materials Irradiation Damage Study at BNL EuCARD N. Simos Effort consists of: IRRADIATION o 200 MeV proton irradiation at.
Microstructural development of HOPG under ion-irradiation ○ Makoto Nonaka 1, Sosuke Kondo 2 and Tatsuya Hinoki 2 1 Graduate school of Energy Science, Kyoto.
Alloy Design For A Fusion Power Plant
Scientific investigations performed at RRC KI for
N. Simos With help from Paola & Elena
Reminder of few basic facts about displacements per atom (dpa)
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;
JOINT INSTITUTE FOR NUCLEAR RESEARCH
Nuclear Energy Fission vs Fusion.
NUCLEAR REACTOR MATERIALS
NEEP 541 Review for Second Exam
«ROSATOM» State Atomic Energy Corporation
XI Reactor Material Science Conference, Dimitrovgrad,
RADIATION CREEP AND SWELLING
Presentation transcript:

FAST NEUTRON IRRADIATION-INDUCED DAMAGE ON GRAPHITE AND ZIRCALOY- 4 TSHEPO MAHAFA University of Johannesburg Supervisor: Dr Emanuela Carleschi (UJ) Co-Supervisor: Dr Chris Franklyn (Necsa) Energy Postgraduate Conference – 14 August 2013 iThembaLABS,Faure, Western Cape iThembaLABS,Faure, Western Cape

Basic Nature of Radiation Damage  The interaction of fast neutrons with atoms of the material results in the displacement of atoms from their positions.  The initial atom to be displaced from its lattice site, the PKA (primary knock-on atom) continues along the lattice path knocking more atoms off their sites.  This in essence leads to the creation of a cascade of displaced atoms. 2

Reactor Technology Development T. Abram and S. Ion, Energy Policy 36(2008)

Burnup Increase per Generation GWd/tU To support higher burnups, improved radiation resistant materials Need to be developed. Gen II Gen I Gen III Gen IV GWd/tU GWd/tU GWd/tU GWd/tU Increase in burnup leads to:  More power generated per fresh fuel  Less fuel needed for fission and reduced fuel costs  Less spent fuel for storage and disposal GWd/tU – GigaWatt day per ton of Uranium 4

Reactor Operating Regime as a function of Temperature and Radiation Dose Thermal Reactors – Gen II and III reactors OPERATING ON A LOWER RADIATION AND TEMPERATURE RANGE High Temperature Reactor (HTR) and Fast Reactor – Gen IV OPERATING ON A HIGHER RADIATION AND TEMPERATURE RANGE IAEA,

Radiation Damage Effects in Materials The continual irradiation of materials by fast neutrons translates into the evolution of the materials microstructure that leads eventually to the physical property changes seen in those materials. Graphite   Irradiation Hardening and Embrittlement  Irradiation Growth  Void Swelling  Irradiation Creep The main object of the project is to understand the underlying mechanism that govern the radiation damage that leads to these effects that are very damaging to the nuclear power reactors Zircaloy-4  Hydrogen Induced Embrittlement  Irradiation Growth  Irradiation Creep  Stress Corrosion Cracking 6

Experimental Approach Sample Damage   The Graphite and Zircaloy-4 samples would be exposed to fast neutrons to induce the damage in a Radio-Frequency Quadropole accelerator located at Necsa.  The accelerator delivers a flux of neutrons per seconds, within an energy range of 1-10MeV's. Characterisation Techniques  Pre and post irradiation examination of the samples would be carried out. The following techniques will be used:  Scanning Electron Microscopy (SEM)  X-Ray Diffraction (XRD)  Raman Spectroscopy  Focussed Ion-Beam and Scanning Electron Microscopy (FIB-SEM) 7

Unirradiated Graphite and Zircaloy-4 Samples SEM Image of Graphite SEM Image of Zircaloy-4 8

Radiation Damage Impact on Nuclear Reactors  Reduced Lifetime of the reactor  Compromised Safety  Increase in downtime  Increased lifecycle costs 9

ANY QUESTIONS? THANK YOU! 10