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Researcher

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Pattrick Calderoni

Scientist/Engineer

Research Areas:
Nuclear instrumentation; Molten salt reactors; Fusion energy

Biography:
Pattrick Calderoni is the Manager of the INL Measurement Science Department and the In-Pile Instrumentation (I2) program, part of the US Department of Energy Nuclear Energy Enabling Technology (NEET) activities. He has personnel and technical oversight over the development of nuclear instrumentation, with emphasis on innovative sensors development for irradiation test of fuels and materials. Dr. Calderoni has more than 20 years’ experience in the development of fission and fusion energy systems and testing of nuclear components. He contributed to the design and operation of experiments in several nuclear research facilities worldwide, including the INL Advanced Test Reactor (ATR) and Transient Reactor Test Facility (TREAT), the Monju reactor in Japan, research reactors in The Netherlands (High Flux Reactor - HFR), Belgium (BR2) and Norway (Halden Boiling Water Reactor - HBWR). His technical and leadership skills consolidated during the 5 years deployed as project manager for ITER, a large-scale scientific experiment under construction in the south of France with the aim of demonstrating the viability of nuclear fusion as energy source. In this capacity he was responsible for the development of the instrumentation and control system (I&C) of two complex components of the ITER machine, the Helium Cooled Lithium Lead (HCLL) and Helium Cooled Pebble Bed (HCPB) Test Blanket Modules (TBMs). Dr. Calderoni previously led the experimental activities of the Safety and Tritium Applied Research (STAR) facility at INL, where he provided significant contributions to the characterization of tritium interaction with materials and the development of liquid metal and molten salt technologies for fusion energy systems.

Digital Profiles:
Education:

​Ph.D.,  Mechanical Engineering - UCLA

M.S., Mechanical Engineering - UCLA

B.A. Nuclear Engineering - Universita' di Bologna, Italy

Affiliations:

​Project Management Institute – Project Management Professional (PMP) certificate
IEEE Instrumentation and Measurement Society

Publications:

Peer-reviewed publications
R. Skifton, J. Palmer, P. Calderoni, Optimization of heat treatment and calibration procedures for high temperature irradiation resistant thermocouples, Instrumentation Science and Tech., 14 (2017) 1-15.


M. Utili, et.al., THALLIUM: An experimental facility for simulation of HCLL In-box LOCA and validation of RELAP5-3D system code, Fusion Engineering and Design, 123 (2017) 102-106.

 
L. Candido, M. Utili, M. Zucchetti, A. Ciampichetti, P. Calderoni, Development of advanced hydrogen permeation sensors to measure Q2 concentration in lead-lithium eutectic alloy, Fusion Engineering and Design, 124 (2017) 735-739.


C. Zeile, I. A. Maione, P. Calderoni, Development of force reconstruction method on EU ITER TBM based on strain measurements, Fusion Engineering and Design, 124 (2017) 376-379.


A. Bukki-Deme, et.al., Experimental investigation of ZrCo getter beds as candidate process for the Tritium Extraction System of the European Test Blanket Modules, Fusion Science and Technology 71 (2017) 527-531.


I. Ricapito, et.al., Current design of the European TBM systems and implications on DEMO breeding blanket, Fusion Engineering and Design 109-111, Part B (2016) 1326-1330.


F. Okino, P. Calderoni, R. Kasada, S. Konishi, Feasibility analysis of vacuum sieve tray for tritium extraction in the HCLL test blanket system, Fusion Engineering and Design 109-111 (2016) 1748-1753.


K. Tian, P. Calderoni, B. Ghidersa, A. Klix, Feasibility Study of a Neutron Activation System for EU Test Blanket Systems, Fusion Engineering and Design 109-111 (2016) 1517-1521.


I. Ricapito, et.al., Tritium Processing for the European Test Blanket Systems: Current Status of the Design and Development Strategy, Fusion Science and Technology 67 (2015) 543-546.


A. Aiello, el.al., Finalization of the conceptual design of the auxiliary circuits for the European test blanket systems, Fusion Engineering and Design 96–97 (2015) 56–63.


G. Barone, et.al., Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop, Fusion Engineering and Design 96–97 (2015) 212–216.


P. Calderoni, et.al., Options and methods for instrumentation of Test Blanket Systems for experiment control and scientific mission, Fusion Engineering and Design 89 (2014) 1126–1130.


I. Ricapito, P. Calderoni, Y. Poitevin, A. Aiello, Technologies and modeling issues for Tritium processing in the European Test Blanket Systems and perspectives for DEMO, Fusion Engineering and Design 89 (2014) 1469–1475.


Y. Poitevin, et.al., Progresses and challenges towards a license to operate European TBM systems in ITER , Fusion Engineering and Design 89 (2014) 1113–1118.


D. Leichtle, et.al., The F4E program on nuclear data validation and nuclear instrumentation techniques for TBM in ITER, Fusion Engineering and Design 89 (2014) 2169–2173.


P. Calderoni, I. Ricapito, Y. Poitevin, Strategy for the development of EU Test Blanket Systems instrumentation, Fusion Engineering and Design 88 (2013) 2440– 2443.


I. Ricapito, P. Calderoni, Y. Poitevin, L. Sedano, Tritium transport modeling for breeding blanket: State of the art and strategy for future development in the EU fusion program, Fusion Engineering and Design, Vol. 87, Issue 5-6 (2012) pp. 793-797.


M. Shimada, et.al., Overview of the US–Japan collaborative investigation on hydrogen isotope retention in neutron-irradiated and ion-damaged tungsten, Fusion Engineering and Design 87 (2012) 1166– 1170.


M. Shimada, et.al., The deuterium depth profile in neutron-irradiated tungsten exposed to plasma, Physica Scripta Transactions, Volume T145 (2011) Article n. 014051.


Y. Oya, et.al., Comparison of deuterium retention for ion-irradiated and neutron-irradiated tungsten, Physica Scripta Transactions, Volume T145 (2011) Article n. 014050.


P. W. Humrickhouse, P. Calderoni, B. Merrill, Implementation of tritium permeation models in the CFD code FLUENT, Fusion Science and Technology, Vol. 60, Issue 4 (2011) pp. 1564-1567.


M. Shimada, T. Otsuka, R. Pawelko, P. Calderoni, J. Sharpe, Overview of Recent Tritium Experiments in TPE, Fusion Science and Technology, Vol. 60, Issue 4 (2011) pp. 1495-1498.


T. Oda, et.al., Development of monte carlo simulation code to model behavior of hydrogen isotopes loaded into tungsten containing vacancies, Fusion Science and Technology, Vol. 60, Issue 4 (2011) pp. 1455-1458.


M. Shimada, et.al., First Result from Deuterium Retention in Neutron-Irradiated Tungsten Exposed to High Flux Plasma in TPE, Journal of Nuclear Materials, Vol. 415, Issue 1 SUPPL (2011) pp. S667-S671.


T. Otzuka, et.al., Application of tritium imaging plate technique to examine tritium behaviors on the surface and in the bulk of plasma exposed materials, Journal of Nuclear Materials, Vol. 415, Issue 1 SUPPL (2011) pp. S769-S772.


P. Calderoni, et.al., An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility, Journal of Nuclear Materials, Vol. 417, Issue 1-3 (2011) pp. 1336-1340.


J.P. Sharpe, et.al., Retention behavior in tungsten and molybdenum exposed to high fluences of deuterium ions in TPE, Journal of Nuclear Materials, Vol. 390-391 (2009) 709-712.


P. Calderoni, J.P. Sharpe, H. Nishimura, T. Terai, Control of molten salt corrosion of fusion structural materials by metallic beryllium, Journal of Nuclear Materials, Vol. 386-388 (2009) pp. 1102-1106.


P. Calderoni, J.P. Sharpe, M. Hara, Y. Oya, Measurement of tritium permeation in flibe (2LiF-BeF2), Fusion Engineering and Design, Vol. 83 (2008) pp. 1331–1334.


L. Schmitz, Y. Tajima, A. Ying, P. Calderoni, Recombination dynamics of metal halides in the presence of vaporized ferritic steel, Fusion Science and Technology, Vol. 52 (2007) pp. 963-968.


P. Calderoni, A. Ying, T. Sketchley, M.A. Abdou, Experimental study of the interaction of ceramic breeder pebble beds with structural materials under thermo-mechanical loads, Fusion Engineering and Design, Vol. 81 (2006) pp. 607-612.


N. Morley, et.al., Overview of Fusion Nuclear Technology in the US, Fusion Engineering and Design, Vol. 81 (2006) pp. 33-43.


A. Ying, et.al., Solid Breeder Test Blanket Modules Design and Analysis, Fusion Engineering and Design, Vol. 81 (2006) pp. 659-664.


P. Calderoni, A. Ying, T. Sketchley, M.A. Abdou, Vapor Condensation Study for HIF Liquid Chambers, Nuclear Instruments and Methods in Physics Research A, Vol. 544 (2005) pp. 111-116.


C. Olson, et.al., Development path for Z-Pinch IFE, Fusion Science and Technology, Vol. 47 (2005) pp. 633-640.


L. Schmitz, P. Calderoni, A. Ying, M.A. Abdou, A novel diagnostic for time resolved spectroscopic argon and lithium density measurement, Journal of Nuclear Materials, Vol. 337-339 (2005) pp. 1096-1100.


M.A. Abdou, et.al., Overview of Fusion Blanket R&D in the US over the Last Decade, Nuclear Engineering and Technology, Vol. 37, Number 5 (2005) pp. 401-422.


P. Calderoni, A. Ying, T. Sketchley, M.A. Abdou, Description of a facility for vapor clearing rates studies of IFE reactors flibe liquid chambers, Fusion Science and Technology, Vol. 39 (2001) pp. 711-715.


Books, proceedings and other publications
P. Calderoni, C. Cabet, Molten salt reactors, in: D. Feron, Nuclear corrosion science and engineering, Woodhead Publishing Ltd (2012) ISBN 978-1-84569-765-5, pp 842-865.


P. Calderoni, M. Angelone, A. Klix, D. Leichtle, Preliminary Engineering Assessment of the HCLL and HCPB Neutron Activation System, Proceeding of the 4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2015, DOI: 10.1109/ANIMMA.2015.7465530.


I. Ricapito, et.al., Tritium Transport Modeling: first achievements on ITER Test Blanket Systems simulation and perspectives for DEMO Breeding Blanket, In proceeding of: IAEA FEC, 2014, St. Petersburg, Russian Federation.


P. Calderoni, J. Vallory, M. Zmitko, I. Ricapito, Y. Poitevin, Overview of Requirements and Design Integration for the ITER EU Test Blanket Systems Instrumentation, In proceeding of: ANIMMA, 2013, Marseille (F), IEEE Catalog Number: CFP1324I-CDR, ISBN: 978-1-4799-1046-5.


P. Calderoni, Hydrogen Permeability in VHTR Heat Exchanger Candidate Materials, Trans. American Nuclear Society, Vol. 102 (2010) pp. 796-797.


P. Calderoni, M. Ebner, R. Pawelko, High-temperature hydrogen permeation in nickel alloys, Proceedings of 5th International Conference on High Temperature Reactor Technology, Prague, Czech Republic, 18-20 October 2010.


R.D. Kolasinski, et.al., Characterization of surface morphology and retention in tungsten materials exposed to high fluxes of deuterium ions in the tritium plasma experiment, Physica Scripta Transactions, Volume T138 (2009) Article n. 14042.


G. Sviatoslavsky, M. Dagher, P. Calderoni, C.P.C. Wong, Quantifying the Advantages of Counter Flow Helium First Wall Cooling, Proceedings of 21st Symposium on Fusion Engineering (2006), Article n.4018935.


C.P.C. Wong, et.al., Overview of the US ITER Dual Coolant Lead Lithium (DCLL) Test Blanket Module Program, Proceedings of 21st Symposium on Fusion Engineering (2006), Article n.4018929.


P. Calderoni, A. Ying, T. Sketchley, M.A. Abdou, Experimental and numerical study of transient condensation of lithium fluoride excited vapors for IFE systems, Proceedings of 20th Symposium on Fusion Engineering (2004).


M. Anderson, Editor, Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling, IAEA publication, Project No. 10-905.


P. Calderoni, On the study of vapor condensation for the assessment of Inertial Fusion Energy liquid chamber clearing, Ph.D. Dissertation, University of California, Los Angeles, 2004.

 

Videos

HTIR thermocouples, iCorps program (2018)

HTTL (2016)

MPFD, KSU intern (2016)

HTIR thermocouples (2011)



 
 
Version: 16.0
Created at 3/23/2018 1:13 PM by Phyllis L. King
Last modified at 3/11/2019 2:29 PM by Phyllis L. King