Europass Curriculum Vitae

Transcription

1 Europass Curriculum Vitae Personal information Surname(s) /First name(s) GUGIU, Elena Daniela Address(es) Str. Pasajul Scarilor nr.2, Bl. 18, sc. F, ap.3, Pitesti, ROMANIA Telephone(s) Office: ext. 624 Mobile: Professional address: Personal address: Nationality Romanian Date of birth Gender Female Occupational field Work experience Dates Occupation or position held Main activities and responsibilities Senior Researcher / Nuclear Reactor Physics & Safety & Nuclear Fuel Performances 2013 onwards -Coordinator of the National R&D Programme on Advanced Nuclear Reactors and Fuel Cycles ; - Romania representative as Observer in the Technical Working Group on Fast Reactors (TWG-FR) at IAEA; - Leader of National Experts Group on Gen III - IV Nuclear Systems; - IAEA-INIS Alternate Liaison Officer a) Expert FP7 ESNII plus Project (Preparing ESNII for HORIZON 2020) b) Expert FP7 ARCADIA Project (Assessment of Regional CApabilities for new reactors Development through an Integrated Approach) c) Expert - R&D activities dedicated to ALFRED Reactor (criticality, transmutations, etc) a) Core safety calculations for ALFRED reactor (criticality computations using MCNP/MCNPX ; DPA, activation and burnup of the structural materials using FISPACT code) b) Identification of the competences and infrastructures needs, addressing the innovative reactors (ALFRED implementation) c) Preliminary evaluation of minor actinides transmutation in ALFRED Reactor

2 Dates Occupation or position held a) Senior researcher/ Task 2.5 leader under Seventh Framework Programme (FP7) Project: LEADER (Lead-cooled European Advanced DEmonstration Reactor); b) Expert IAEA Contract Large Sample Neutron Activation Analysis (NAA) Facility and Methodology Development. c) Expert FP7 CARBOWASTE Project d) Expert- FP7 NEWLANCER Project Main activities and responsibilities a) Evaluation of the neutron damage (DPA) and radiological protection for LFR (Lead Fast Reactor) of industrial size and for ALFRED (European LFR Technology demonstrator/pilot Plant); b) Monte Carlo simulations of the NAA related experiments. Gamma spectrometry. Efficiency calibration of the Ge spectrometer by measurements and Monte Carlo simulations. c) Qualitative and quantitative evaluations of the irradiated graphite composition using MCNPX and FISPACT codes. Dates Occupation or position held PhD, Senior researcher Main activities and responsibilities - Working stage (6 months Oct. 2008/April 2009) at ENEA-Bologna, Italy, in the frame of FP6 ELSY (European Lead cooled Systems) Project. Evaluations of the neutron damage and the activation of the reactor components (MCNP/MCNPX and FISPACT codes). Dose computations. - Expert IAEA Contract Large Sample NAA Facility and Methodology Development. Monte Carlo simulations of the NAA related experiments. Gamma spectrometry. -1 Expert FP6 Project: Integrated Infrastructure Initiatives for Material Testing Reactor Innovations (MTR+I 3 ). Monte Carlo simulations of the TRIGA and ACPR reactors and the associated experiments. -2 Working stage (3 months June-September 2007) at ENEA-Bologna, Italy, in the frame of FP6 ELSY (European Lead cooled Systems) Project. Monte Carlo analysis of new concepts of reactivity control designed to control the reactor radial power distribution. -3 Invited lecturer at the University of Bologna, Italy, in the frame of Second level Master Course titled: Design and management of nuclear advanced systems (June 2011); -4 Invited lecturer at the University of Bologna, Italy, in the frame of Second level Master Course titled: Design and management of nuclear advanced systems (April 2010);

3 - Invited lecturer at the University of Bologna, Italy, in the frame of Second level Master Course titled: Design and management of nuclear advanced systems (June 2009). Dates Occupation or position held Senior researcher Main activities and responsibilities -5 neutron spectrometry of type Bonner sphere: Monte Carlo simulations of the neutron spectrometer developed at INR in order to evaluate the response function matrix, measurements and Monte Carlo simulations for calibration purposes; Occupation or position held Main activities and responsibilities Name and address of employer Type of business or sector -6 Monte Carlo simulations and measurements related to the implementation of the thermal column and the Sigma-Sigma facilities at the Romanian TRIGA reactor. -7 Neutronic characterization of the thermal flux cavity (in the thermal column) and of the ΣΣ irradiation facility (MCNP5 computations). Measurements (foil activation techniques) and unfolding procedure for flux and spectrum evaluations; comparison with the computed values. -8 Criticality computations for different CANDU fuel projects (MCNP, MCNPX and MONTEBURNS codes). -9 Evaluations of the dose and heating of the cobalt adjuster rods irradiated in CANDU reactors; -10 Partner in: Action Sheet 3 form of cooperation between ICN-Piteşti and DOE- USA on Nuclear Analysis and Radiation Shielding, Participant in: IAEA contract no. 7948/R2 PC Based System for Absolute Neutron Flux- Spectrum Measurements, Dates Junior researcher -11 Monte Carlo simulation of the self-powered detector sensitivities; -12 Isotope identification by qualitative and quantitative analyses; -13 Gamma spectrometry; -14 Neutron flux-spectrum measurements using the foil activation method in order to: design and characterize the irradiation device used for silicon doping by neutron transmutation doping technique; -15 Evaluation of the neutron flux distribution of the irradiation locations used for various sample irradiations; -16 Qualitative and quantitative identification of the sample isotopes; -17 Characterization of a graphite pile type irradiation facility for thermal neutron flux measurements. Institute for Nuclear Research, Street: Campului no.1, PO Box 078, Pitesti-Mioveni, ROMANIA Nuclear research Education and training Dates

4 Title of qualification awarded Principal subjects/occupational skills covered Name and type of organisation providing education and training Ph.D., Physics Thesis title: Contributions to the Development of the Monte Carlo Techniques in the Reactor Physics and Neutrons Dosimetry University of Bucharest, Romania Dates April 2001 Title of qualification awarded Advanced MCNP code user Principal subjects/occupational skills Monte Carlo simulation of the radiation transport covered Name and type of organisation providing education and training Los Alamos National Laboratory Location: Imperial College, London, UK. Dates Title of qualification awarded Nuclear Reactor Physics Engineer Diploma Principal subjects/occupational skills Nuclear Reactors Physics; Radiation Dosimetry covered Name and type of organisation University of Bucharest, Romania providing education and training Personal skills and competences Mother tongue(s) Romanian Other language(s) Self-assessment Understanding Speaking Writing European level (*) Listening Reading Spoken interaction Spoken production English B2 Independent user B2 Independent user B2 Independent user B2 Independent user B2 Independent user French B2 Independent user B2 Independent user B2 Independent user B2 Independent user B2 Independent user Italian B2 Independent user B2 Independent user B1 Independent user B1 Independent user A2 Basic user Social skills and competences -Flexible and able to work in multicultural teams and to build working relationships -A results-oriented person having the ability to critically analyze and evaluate my own findings and those of others - Dedicated individual achieving a reputation for consistently going beyond what is required. Organisational skills and competences Computer skills and competences Additional information Organizer of the Invited Sessions (titled: Informatics in Support of Nuclear Area Applications on Nuclear reactor and Power Plants, Accelerators, Nuclear Medicine, etc) of the CITSA 2005 Conference, Orlando, Florida, USA. Licensee for various computer codes used in radiation transport: MCNP / MCNPX, EASY-2010, SERPENT, MONTEBURNS, SAMPO Competent with Microsoft Office programmes. For references the following scientists could be contacted: Dr. Giacomo Grasso : giacomo.grasso@enea.it Dr. Ronald James Ellis: ellisrj@ornl.gov Dr. Didier De Bruyn: ddbruyn@sckcen.be Ing. Alessandro Alemberti: alessandro.alemberti@ann.ansaldo.it Annexes 1)Short list of publications

5 Annex 1 1 D. Dobrea, Cs. Roth, D. GUGIU, N. Fulger, Al. Stefan - Silicon Doping by Neutron Transmutation Doping at TRIGA-ROMANIA, Proc. of the TRIGA Conference D. Dobrea, Cs. Roth, D. GUGIU, M. Farcas - Neutron Measurements for CANDU-type Fuel Characterization, Proc. of the TRIGA Conference D. Dobrea, Cs. Roth, D. GUGIU, A. Popa - A Graphite Pile Type Irradiation Facility for Thermal Neutron Flux Measurements in the nv range, SIEN Cs. Roth, D. Dobrea, D. GUGIU, A. Popa, N. Fulger - Device and methods for thermal neutron flux measurements in the range n/cm2s, National Conference on Energy, Neptun, D. Dobrea, D. GUGIU, Cs. Roth, N. Fulger - Simulation of the platinum detector response, COG/IAEA First International Co-operation in Information Exchange and Co-operative Research Technical Meeting Nuclear and Radiological Safety CANDU Owners Group/IAEA Technical Meeting, D. Dobrea, N. Fulger, Cs. Roth, D. GUGIU - Analog to Digital Conversion using Successive Approximations Method in Gamma Ray Spectrometry, COG/IAEA First International Co-operation in Information Exchange and Co-operative Research Technical Meeting Nuclear and Radiological Safety CANDU Owners Group/IAEA Technical Meeting, D. Dobrea, Cs. Roth, N. Fulger, D. GUGIU - PC Based Systems for Reactor Physics Measurements, IAEA Technical Committee Meeting on "Improvement of the Data Acquisition for Research Reactors and Experiments, Cs. Roth, D. Dobrea, N. Fulger, D. GUGIU - Devices and methods for CANDU Reactor Start-up Instrumentation Tests, Proceedings of International Symposium on Nuclear Energy NPP Operation and Maintenance - SIEN 99, Bucureşti, Oct Cs. Roth, I. Gârlea, D. GUGIU, A. Datcu, C. Gârlea, M. Pavelescu - Thermal flux standard implementation strategy at TRIGA reactor thermal column, Proceedings of International Metrology Conference, Bucharest, sept ISBN: D. GUGIU, M. Constantin, - Monte - Carlo Evaluation (using MCNP-4C code) of the Void Reactivity Coefficient and Pin Power Factors for a 43-Fuel Pins CANDU Cell, Proceedings of

6 CMMSE2002 Conference, Alicante, Spain. 11 M. Constantin, D. GUGIU, V. Balaceanu - Void Reactivity and Pin Power Calculation for a CANDU Cell using the SEU-43 Fuel Bundle, Annals of Nuclear Energy 30, D.GUGIU Monte Carlo Simulation of the Large Sieve Tray Towers Monitoring Process, Proceedings of the Fifth General Conference of the Balkan Physical Union BPU5, Serbia, D. Dobrea, I. Dumitrache, D. GUGIU,- Computing neutron detector response to power reactor mechanical structure vibrations, et all, Annals of Nuclear Energy 31 (2004). 14 Cs. Roth, I. Gârlea, D. Dobrea, L. Aioanei, C. Kelerman, C. Gârlea, D. GUGIU, A. Datcu, M. Preda, M. Pavelescu The Secondary Intermediate-Energy Standard Neutron Field Development at the Romania TRIGA Reactor, Nucl. Instr. & Meth. in Phys. Research A 522, ( ), D. GUGIU et all, -An Analysis of the Nuclear Data Libraries Impact on the Criticality Computations Performed Using Monte Carlo Codes, published by American Institute of Physics (AIP), vol. 769 (2005). 16 D. GUGIU, Cs. Roth,- A method for evaluation the activity of the reactor components, EUR 22136EN, Belgium, D. GUGIU, I. Dumitrache, - Monte Carlo Estimation of the Dose and Heating of Cobalt Adjuster Rods Irradiated in the CANDU 6 Reactor Core, Radiation Protection Dosimetry, vol. 114, 1-4,(2005). 18 D. GUGIU, R.J.Ellis,- The Applications of Monte Carlo Codes to Romania TRIGA and CANDU Reactors, The Monte Carlo Method: Versatility Unbounded In A Dynamic Computing World Chattanooga, Tennessee, USA, April 17 21, D. GUGIU, V. Hristea, - Neutronic Analysis of CANDU-SEU Fuel Bundles using Monte Carlo Codes, Proceedings of The American Nuclear Society s 14 th Biennial Topical Meeting of the Radiation Protection and Shielding Division, Carlsbad New Mexico, USA. April 3-6, D. GUGIU, Cs. Roth,- Radioactivity Estimation using Monte Carlo Codes, Proceedings of The American Nuclear Society s 14 th Biennial Topical Meeting of the Radiation Protection and Shielding Division, Carlsbad New Mexico, USA. April 3-6, M. Sarotto, C. Artioli, G. Grasso, D. GUGIU, A. Travleev - ELSY core design static, dynamic and safety parameters with the open square FA, Technical report DEL/09/08 in the frame of FP6 ELSY Project (European Lead-cooled System), D. GUGIU, G. Grasso, C. Petrovich - Reactor Shielding Design for Selected Core, Technical report DEL/09/011 in the frame of FP6 ELSY Project (European Lead-cooled System), D. GUGIU, Cs. Roth, A. Ghinescu, - Counting efficiency computation for LSNAA, presented at Modern Trends in Activation Analysis-13, March, 2011,Texas, USA. 25 D. GUGIU - Considerations Regarding the Tantalum Element Behavior in Fast Reactors, Journal of Nuclear Research and Development, Vol.1, 2011.

7 26 D. GUGIU, C. Petrovich - ETDR core: DPA rates in the main components, activation, doses, Technical report TEC in the frame of FP7 LEADER Project (Lead-cooled European Advanced Demonstrator Reactor), G. Glinatsis, D.E. GUGIU Long-Lived Small LMFR. Core Design Challenges, Journal of Nuclear Research and Development, Vol.4, D. GUGIU, G. Grasso, C. Petrovich - ELFR core: DPA rates in the main components, activation, doses, Technical report TEC in the frame of FP7 LEADER Project (Lead-cooled European Advanced Demonstrator Reactor), Csaba Roth, Dumitru Barbos, Daniela GUGIU, Adrian Datcu, Dumitru Dobrea, Marin Preda, Mihai Gligor & Madinka Bright Mweetwa, -Irradiation and measurement devices and methods development for LSNAA applications at the TRIGA-ACPR core, Journal of Radioanalytical and Nuclear Chemistry, Volume 291, Number 2 (2012). 30 D.E.GUGIU, C. Petrovich Neutronic Analysis of the Structural Materials used in Heavy Liquid Cooled Fast Reactors, Journal of Nuclear Research and Development, Vol.5, G. Grasso, C. Petrovich,Davide Mattioli, C. Artioli, D. Gugiu, The core design of ALFRED, a demonstrator for the European lead-cooled reactors, Nuclear Engineering and Design,10/2014;