1. 20141119_KuijperJC 1/9 [2014-11-19/13:31]
Curriculum Vitae
NAME : James C. Kuijper (Jim)
PROFESSION : Senior Consultant - Nuclear Reactor Physics Specialist
DATE OF BIRTH : 07 April 1961
NATIONALITY : The Netherlands
EDUCATION LEVEL : PhD (Nuclear Reactor Physics)
LANGUAGES : Dutch, English, German
COMPUTER : Fortran, Linux/Unix (C-shell, Bourne-shell, scripting), MS Office/Project, HTML
CONTACT : M jimkuijper@gmail.com
T +31 6 4022 9728
EDUCATION
1988 – 1992 Delft University of Technology, Delft (NL), Nuclear Reactor Physics, PhD (Dr).
1979 – 1986 Twente University of Technology, Enschede (NL), Applied Physics, MSc (Ir).
Courses
1994 – 2006 “Reactor Physics, Criticality and Shielding Seminar”.
ANSWERS Software Service, AEA Technology, U.K./SERCO Assurance, U.K.
(Annual 3d/y seminar for specialists and users of ANSWERS Software) Contributions on the subjects, (i) PWR, (ii) HTR reactor physics, space-time kinetics and (iii) uncertainty propagation in burn up calculations.
Nov 2011 “INIS Training Seminar 2011” (3 days).
IAEA, International Nuclear Information System (INIS), Vienna, Austria
2004 “DANESS” (system dynamics code for the holistic assessment of nuclear energy system strategies).
Luc van den Durpel, LISTO bvba/Argonne National Laboratory (USA)
Mar/Apr 2004 “OSCAR-3” (core physics & core design).
NECSA, South Africa
June 1995 Project management.
Kern Consult, Bussum, the Netherlands
Nov 1984 Radiation Protection level 3.
Interfaculty Reactor Institute, Delft University of Technology (NL)

2. 20141119_KuijperJC 2/9 [2014-11-19/13:31]
EXPERIENCE
May 1992–Now Netherlands Energy Research Foundation (ECN)/Nuclear Research & Consultancy Group (NRG), Petten (NL).
1998-now Business Unit “Irradiation & Development” (I&D), Physics & Metrology team, Nuclear Research & Consultancy Group (NRG).
1992-1998 Business Unit “Nuclear Energy”, Netherlands Energy Research Foundation (ECN).
Senior Consultant (since February 2006)
2010-2014
 Preparation of an overview presentation on plutonium and minor actinide management in thermal HTRs for the IAEA Technical Meeting on Development of “Deep-burn” Concepts using High Temperature Gas Cooled Reactor (HTGR) coated Particle Fuel for Incineration of Nuclear Waste, Surplus Fissile Materials and Plutonium without Recourse to Multiple Processing, IAEA Headquarters, Vienna, 5-7 August 2013 (see http://www.iaea.org/NuclearPower/Downloadable/Meetings/2013/2013-08-05-08-07-TM- NPTD/meeting_report.pdf)
 (Since January 1994) Member of the Reactor Safety Committee of the Petten (NL) research site, as expert in nuclear reactor physics and space-time kinetics as well as nuclear criticality safety. This Reactor Safety Committee advices the managements of NRG, ECN and the Institute for Energy and Transport (IET) of the Joint Research Centre (JRC) of the Commission of the European Communities (CEC) in all matters concerning nuclear safety of the nuclear installations at the Petten research site, including (experiments in) the High Flux Reactor (HFR), the Hot Cell Laboratories (HCL), the Molybdenum Production Facility (MPF) and the Waste Storage Facility (WSF).
 (January 2007 – October 2014) Member of the Staff Council (“Ondernemingsraad”) of NRG. Main topics: strategy, finance, safety, health, well-being, environment. Heavily involved (advice and consent to the general manager) in the re-structuring process of NRG in 2014.
 Euratom representative in Generation IV International Forum (GIF) Very High Temperature Reactor (VHTR) Computational Methods Validation & Benchmarking (CMVB) (provisional) Project Management Board (GIF/VHTR/CVMB PMB).
 (Since August 2008) Liaison officer for the Netherlands of the IAEA International Nuclear Information System (INIS) (see http://www.iaea.org/inis/).
 (Since 1995) Teacher of nuclear reactor physics and kinetics in courses on Nuclear Technology of NRG (for internal and external students), as well as in basic training courses for nuclear reactor operators for research reactors and nuclear power plants.
 Coaching and supporting colleagues and guest scientists in the use of reactor physics simulation code systems (e.g. WIMS, DRAGON and PANTHER) and understanding of underlying methodologies.
 Euratom FP7 project CP-ESFR: task leader for study of impact of Minor Actinide fuel on transient behavior of Sodium-cooled Fast Reactors (SFR); involved in the assessment of the influence of Minor Actinides on reactivity feedback coefficients, etc.
 Euratom FP7 project F-BRIDGE: assessment of the influence of the use of sphere-pac fuel on (E)SFR reactor behaviour (in conjunction with CP-ESFR).

3. 20141119_KuijperJC 3/9 [2014-11-19/13:31]
 Euratom FP7 ARCHER (HTR) project, monitoring and supporting the upgrade project of the ASTRA critical facility of the Kurchatov Institute, Moscow (ISTC project #685.2).
 (March/April 2011) Teacher in criticality safety assessment course for URENCO.
 (October-December 2011) Review of criticality safety assessment for internal transport of LFR (Petten Low Flux Reactor) fuel elements.
 (September 2011-February 2012) Assessment of criticality safety issues as part of the Complementary Safety Margin Assessment (“Stress Test”) of the nuclear installations of the Petten research site.
 RECREATE project of the European 7th Framework Program: assessment of the feasibility of a cruiser aircraft with nuclear propulsion in a new cruiser-feeder system of air transport.
2006-2009
 Coordinator of the PUMA (“Plutonium and Minor Actinides Management in Thermal High- Temperature Reactors”) project of the Euratom 6th Framework Program (EC contract no. FP6-036457; Total budget: M€ 3.7; 15 partners from the EU, 1 from the USA; see ftp://ftp.cordis.europa.eu/pub/fp6-euratom/docs/20101105-puma-1006-d411g-publishable- final-activity-report-nrg-104869_en.pdf).
 (July 2006) Guest lecturer at the Madrid University of Technology (Spain) on combined Monte Carlo neutronics, inventory calculations and uncertainty propagation.
 (2006/2007) Teacher in a tailor-made course on criticality safety assessment for external companies. Co-developer of this course.
Task Manager Reactor Physics (2001-2006)
2005
 Software development lead: integration of the CASEMATE methodology for propagation of uncertainties in cross sections through burn-up calculations with the OCTOPUS system for combined Monte-Carlo neutronics (MCNP code) and detailed burn-up (ORIGEN or FISPACT code).
 Involved in the development of a special course on criticality safety assessment for a confidential customer.
2000 – 2004
 Study of reactor physics aspects of the use of Th/Pu-MOX in LWRs, analysis of cross section uncertainty propagation in burn up calculations, and the use of Pu in pebble-bed HTRs with continuous recycling. These activities were part of the THORIUM, VALMOX and HTR-N/N1 projects, respectively, of the Euratom Fifth Framework Program.
 Work Package manager in the Euratom HTR-N/N1 project for the Work Package on the analysis of several HTR concepts with different fuel cycles.
2002 – 2003
 Software development: involved in the development of a Monte-Carlo based code system (ELNINJO) to generate broad group cross sections to enable the calculation of reactor physics and reactor kinetics parameters in the framework of new licensing calculations for the Petten High Flux Reactor (HFR). Development of theoretical background for this method.

4. 20141119_KuijperJC 4/9 [2014-11-19/13:31]
 Software development: involved in the modernization and modularization of the OCTOPUS code system, which has been developed at NRG to enable combined (Monte Carlo) neutronics and nuclide inventory evolution calculations.
Research scientist (1992 – 2000)
 (Nov/Dec 1993) Co-organizer of a workshop on 3-D transient core codes.
 (1994) Participation in the preparation of the Safety Report and the Safety Analysis Report for the Dodewaard nuclear power plant as co-author of the sections concerning reactivity transients (1994).
 (1994ff) Lead the development of the simulation code system PANTHERMIX for combined steady state, depletion and transient reactor physics and thermal-hydraulics analysis of the High-Temperature Gas-Cooled Reactor (HTR) program at ECN and NRG.
 (1994-present) Coaching colleagues and guest employees of NRG in the use of the WIMS and PANTHER/PANTHERMIX codes for performing reactor physics calculations on several different reactor types (PWR and HTR).
 (1994-2000) Mentor for a PhD-student from Delft University of Technology on the subject of HTR reactor dynamics. Member of the PhD examination committee.
 (Summer 1995) Guest scientist at Berkeley Technology Centre of Nuclear Electric Plc., Berkeley, Gloucestershire, U.K. Re-analysis of the Callaway PWR cycle 1 and 2 physics measurements, using the LWRWIMS en PANTHER codes for steady-state, depletion and transient calculations.
 (1995-1999) Lead the development of a code system for uncertainty propagation in combined spectrum and burn up calculations (CSS1SMAT/CASEMATE) in the Euratom 4th Framework Program.
 Review of Acceptance Test Procedures (ATP) for the new simulator of the Borssele NPP with focus on reactivity aspects of the system behaviour.
January 1988–May 1992
Interfaculty Reactor Institute – Delft University of Technology (NL)
Research scientist on reactor physics and thermodynamics of gaseous core fission reactors.
March 1986–August 1987
Royal Netherlands Navy – Physics and Electronics Laboratory, The Hague (NL)
Fulfilment of military duty by research on and software development for passive towed-array sonar signal processing.

5. 20141119_KuijperJC 5/9 [2014-11-19/13:31]
APPENDIX – List of publications and presentations
J.C. Kuijper, “Pu and MA Management in Thermal HTR, Quo Vadis? – Insights from the Euratom PUMA project”, Invited presentation at the IAEA Technical Meeting on Development of “Deep-burn” Concepts using High Temperature Gas Cooled Reactor (HTGR) coated Particle Fuel for Incineration of Nuclear Waste, Surplus Fissile Materials and Plutonium without Recourse to Multiple Processing, IAEA Headquarters, Vienna, Austria, 5-7 August 2013. Presented by F. Reitsma (Calvera/IAEA) (see
http://www.iaea.org/NuclearPower/Downloadable/Meetings/2013/2013-08-05-08-07-TM- NPTD/15_puma.pdf).
J.C. Kuijper et al., “Plutonium and Minor Actinide Management in Thermal High- Temperature Gas-Cooled Reactors - Publishable Final Activity Report”, Report PUMA-1006- D411g, Rev. 1, November 2010 (see
ftp://ftp.cordis.europa.eu/pub/fp6-euratom/docs/20101105-puma-1006-d411g-publishable- final-activity-report-nrg-104869_en.pdf).
J.C. Kuijper et al., “Pu and MA Management in Thermal HTGRs - Impact at Fuel, Reactor and Fuel Cycle Levels”, Proceedings of the 4th International Topical Meeting on High Temperature Reactor Technology HTR2008, Washington DC, USA, September 28-October 1, 2008.
Nuria García-Herranz, Oscar Cabellos, Javier Sanz, Jesús Juan, J.C. Kuijper, “Propagation of statistical and nuclear data uncertainties in Monte Carlo burn-up calculations”, Annals of Nuclear Energy, Volume 35, Issue 4, pp 714 – 730, April 2008 (accepted 26 July 2007).
J.C. Kuijper & J.B.M. de Haas, “HTGR Core Transient Analyses”, Presentation at IAEA Technical Meeting on Safety Aspects of Modular HTGRs, Beijing, P.R. China, October 23- 26, 2007.
J.C. Kuijper, “PUMA - Plutonium and Minor Actinides Management in Thermal High- Temperature Gas-Cooled Reactors”, Proc. 10th ISTC Scientific Advisory Committee Seminar “Advanced Nuclear Fuel Cycle for the 21st Century”, Nizhniy Novgorod, Russian Federation, September 24-27, 2007.
J.C. Kuijper, “Plutonium and Minor Actinides Management in Thermal High-Temperature Reactors”, Proc. ENC 2007, Brussels, Belgium, 16 – 20 September, 2007.
J.C. Kuijper, “Plutonium and Minor Actinides Management in Thermal High-Temperature Reactors – The EU FP6 Project PUMA”, Proc. ICENES 2007, Instanbul, Turkey, June 3-8, 2007.
J.C. Kuijper, “PUMA – Plutonium and Minor Actinides management in Thermal High- Temperature reactors”, Proc. ICAPP 2007, Nice, France, May 13-18, 2007.

6. 20141119_KuijperJC 6/9 [2014-11-19/13:31]
J.C. Kuijper, S.C. van der Marck and A. Hogenbirk, “Using homogenized macroscopic group cross sections in continuous-energy Monte Carlo neutron transport calculations with MCNP”, Proc. Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications (M&C + SNA 2007), Monterey, California, April 15 - 19, 2007.
J.C. Kuijper, “Combined Monte Carlo Neutronics, Burn-up and Uncertainty Propagation Calculations: Details & Pitfalls”, Invited presentation, IKET, Forschungszentrum Karlsruhe,
Germany, 7. November 2006.
J.C. Kuijper, “Duurzame kernenergie - Geavanceerde splijtstofcycli en materialen”, Invited presentation, Koninklijke Nederlandse Academie van Wetenschappen (Royal Netherlands Academy of Sciences), Derde najaarsbijeenkomst Verkenning Onderzoek Duurzame Energieconversie, 13. October 2006.
Phlippen, P.W, Bodewig, T., Tittelbach, S., Kuijper, J.C., da Cruz, D.F., Worral, A., Thomas, G.M., “Code-to-code benchmark for (Th/Pu)O2-burn-up in PWR“, Proc. Jahrestagung Kerntechnik, Aachen, Germany, 16 - 18 May, 2006.
J.B.M. de Haas, J.C. Kuijper & J. Oppe, ”Burnup and transient analysis of a HTR-400 design loaded with PuO2”, Proc. HTR2006, Sandton, Gauteng, South Africa, 1-4 October, 2006.
J.C. Kuijper et al., “SCENTRAN-Pu - Scenario and transient studies of a PWR with Pu-IMF fuel”, NRG report 21615/06.73747/I, 18 July 2006.
J.C. Kuijper, “Details and pitfalls of Monte Carlo neutronics and detailed burn-up calculations; Uncertainty and sensitivity in inventory calculations”, Invited lectures, Seminar Universidad Polytechnica de Madrid/Department of Nuclear Engineering (UPM/DIN), Madrid, Spain, 30 June - 3 July 2006.
S.C. van der Marck, J.C. Kuijper & J. Oppe, “Homogenized Group Cross Sections by Monte Carlo”, Proc. PHYSOR 2006.
J.C. Kuijper et al., “HTGR Reactor Physics and Fuel Cycle Studies”, Nuclear Engineering and Design 236, 615 - 634, 2006 (accepted 31 October 2004).
J.B.M. de Haas, J.C. Kuijper & J. Oppe, “HTR Core Physics and Transient Analyses by the PANTHERMIX Code System”, Proc. M&C 2005, Avignon, France, 12 - 15 September 2005.
J.C. Kuijper, J. Oppe, R. Klein Meulekamp & H. Koning, “Propagation of Cross Section Uncerntainties in Combined Monte Carlo Neutronics and Burnup Calculations”, Proc. M&C 2005, Avignon, France, 12 - 15 September 2005.
J.B.M. de Haas and J.C. Kuijper, “Feasibility of burning first- and second generation plutonium in pebble bed high-temperature reactors”, Nuclear Technology 151 no. 2, 192 - 200, August 2005.
R. Klein Meulekamp, J.C. Kuijper and M. Schikorr, “Point Genetics: A New Concept to Assess Neutron Kinetics”, Nucl. Sci. Eng. 149 no. 2, 237 - 245, February 2005.

7. 20141119_KuijperJC 7/9 [2014-11-19/13:31]
J.C. Kuijper et al., “Definition of Common Parameters and Reference HTR Designs for HTR-N[1]”, NRG report 20570/04.61610/C, Deliverable 3.1.1 for EU FP5 project HTR-N, August 2004.
J. Oppe & J.C. Kuijper, “OCTOPUS_TNG Reference Manual”, NRG Report 20748/03.54103/C, 26. November 2004.
J.C. Kuijper et al., “HTR-N Reactor Physics and Fuel Cycle Studies”, Proc. 2nd International Topical Meeting on High Temperature Reactor Technology (HTR), Beijing, P.R. China, 22- 24 September 2004.
J.C. Kuijper et al., “HTR-N Plutonium Cell Burnup Benchmark: Definition, Results & Intercomparison”, Proc. PHYSOR 2004, Chicago, IL, USA, 25 - 29 April 2004.
J.C. Oppe & J.C. Kuijper, “Plutonium HTR Cell Burnup benchmark: Several Calculation Methods and Their Results”, NRG Report 20780/03.55862/P, 23. January 2004.
J.B.M. de Haas & J.C. Kuijper, “Feasibility of Burning First and Second Generation Plutonium in a Pebble Bed HTR”, Proc. ANFM-III, Hilton Head Island South Carolina, USA, American Nuclear Society, 5-8 October 2003; also published as NRG report 20570/03.56305/C.
B. Lance, S. Pilate, R. Jacqmin, A. Santamarina, D. Bernard, B. Verboomen, J.C. Kuijper, “VALMOX - Validation of Nuclear Data for High-Burnup MOX Fuels”, Nuclear Engineering & Design, Vol. 235, Issues 2 – 4, pp 269 – 278, February 2005 (accepted 31 August 2004) .
B. Lance, S. Pilate, R. Jacqmin, A. Santamarina, D. Bernard, B. Verboomen, J.C. Kuijper, “Validation of High Burnup MOX Fuels calculations (VALMOX)”, Proc. FISA 2003, European Commision, Jean Monnet Building, Luxembourg, 10 - 13 November 2003.
R. Klein Meulekamp, M. Schikorr & J.C. Kuijper, “Point Genetics : A new concept to assess dynamic behaviour in accelerator driven systems”, Proc. Nuclear Mathematical & Computational Sciences (M&C, ANS), Gatlinburg, TN, USA, 6 - 11 April 2003 also published as NRG report 20571/03.53106/P, 17. April 2003.
J.C. Kuijper & S.C. van der Marck, “Reactivity weighting factors for HFR-LEU transient analyses”, NRG report 25147/03.53600/C, 6. June 2003.
S.C. van der Marck, J.C. Kuijper & A. Hogenbirk, “Reactor neutronics data for use in HFR- LEU transient analyses”, NRG report 25147/03.53597/C, 6. June 2003.
J.C. Kuijper, J. Oppe, J.B.M. de Haas and D.F. da Cruz, “DETAILS OF MODELLING HTR CORE PHYSICS: THE USE OF PSEUDO NUCLIDE TRACES”, Proc. SNA 2003, Paris, France, 22 - 24 September 2003.
R. Klein Meulekamp, A. Hogenbirk & J.C. Kuijper, “Relation between the Intrinsic Core Criticality and the Multiplication of the Source in ADS applications”, NRG report 20792/02.50732/I, 9. December 2002.

8. 20141119_KuijperJC 8/9 [2014-11-19/13:31]
J. Oppe, J.C. Kuijper & S.C. van der Marck, “ELNINJO Manual”, NRG report 25138/02.46889/C, 1. April 2002.
J.C. Kuijper, J.B.M. de Haas & J. Oppe, “HTR core physics analysis at NRG”, Proc. 1st International Topical Meeting on High Temperature Reactor Technology (HTR), European Nuclear Society and International Atomic Energy Agency, Petten, the Netherlands, April 2002.
A.I. van Heek, J.C. Kuijper, J.B.M. de Haas, J. Oppe & E. Mulder, “Comparison of core calculations on the Pebble Bed Modular Reactor”, NRG report 910516/01.41920/P, 27. November 2001.
J.C. Kuijper et al., “Present status in the Netherlands of research relevant to high-temperature gas-cooled reactor design”, Proc. Second Information Echange Meeting on Basic Studies in the Field of High-temperature Engineering, OECD/NEA, Paris, France, October 2001; also published as NRG report 20631/01.43344/P
J. Oppe, J.C. Kuijper, J.B.M. de Haas, E.C. Verkerk & H.T. Klippel, “Modeling of continuous reload HTR systems by the PANTHERMIX code system”, Proc. M&C 2001, Salt Lake City, Utah, USA, September 2001
J.L. Kloosterman & J.C. Kuijper, “VAREX, A Code for Variational Analysis of Reactivity Effects: Description and Examples”, Proc. M&C 2001, Salt Lake City, Utah, USA, September 2001.
H.Th. Klippel, J.C. Kuijper, J.B.M. de Haas, J. Oppe & E.C. Verkerk, “PBMR Burn-in core analysis - PBMR Benchmark with PANTHERMIX”, NRG report 20429/00.38175/C (Rev. 1), December 2000.
H. van Dam & J.C. Kuijper (ed.), “ICENES 2000 – The Tenth International Conference on Emerging Nuclear Energy Systems”, Proceedings, ISBN 90-805906-2-2, September 2000.
J.C. Kuijper et al., “Sensitivity and uncertainty assessment associated to burnup calculations”, Proc. ANS Topical Meeting on Advances in Reactor Physics and Mathematics and Computation into the Next Millennium “PHYSOR 2000”, May 7 - 12, 2000, Pittsburg, Pennsylvania, USA, reprint in NRG report 20420/01.38985/P, January 2001.
S. Pilate, T. Maldague, R. Jacqmin, Ch. Chabert, S. van Winckel, Ch. de Raedt, J.C. Kuijper, G. Nicolau, A. Ventura, “Nuclear data for advanved MOX fuels”, Report EURATOM EUR 19126 EN, ISBN 92-828-8491-0, 2000.
J.C. Kuijper et al., "Reactor physics calculations on the Dutch small HTR concept", Proc. IAEA TCM on HTGR Technology Development "Commercializing the HTGR", Johannesburg, Republic of South Africa, 13 - 15 November 1996.
J.C. Kuijper, "Final PANTHER solution to the NEA-NSC 3-D PWR core transient benchmark", Report ECN-R--96-005, ECN, The Netherlands.

9. 20141119_KuijperJC 9/9 [2014-11-19/13:31]
J. Oppe, J.B.M. de Haas & J.C. Kuijper, "PANTHERMIX - A PANTHER - THERMIX interaction", ECN-I--96-022, ECN, The Netherlands.
B.C. Zhang & J.C. Kuijper, "Results for the LEUPRO 1 - 6 whole reactor calculations with WIMS-E", Report ECN-I--96-007, ECN, The Netherlands.
B.C. Zhang & J.C. Kuijper, "Results for the LEUPRO 1 - 6 cell calculations with WIMS-E", Report ECN-I--95-007, ECN, The Netherlands
J. Oppe & J.C. Kuijper, "WILITO version 9502 – WIMS Library Tool", Report ECN-CX-- 95-101, ECN, The Netherlands.
J. Oppe & J.C. Kuijper, "WILITO - Wims Library Tool", Report ECN-CX--94-187, ECN, The Netherlands.
J.C. Kuijper, "PANTHER solution to the NEA-NSC 3-D PWR core transient benchmark", Report ECN-R--94-023, ECN, The Netherlands.
H. van Dam & J.C. Kuijper, "Dynamics of a gaseous oscillating-core reactor", Proc. 7th International Conference on Emerging Nuclear Energy Systems, Makuhari, Chiba, Japan, September 20 - 24, 1993.
J.C. Kuijper et al., "Gas dynamics models for an oscillating gaseous core fission reactor", Progress in Nuclear Energy, Vol. 26, No. 3, 1991, 217 – 230.
J.C. Kuijper, "A calculational study on reactor physics and thermodynamics of a gaseous core fission reactor", Ph.D thesis, Delft University of Technology, ISBN 90-73861-06-3, June 1992.
J.C. Kuijper & H. van Dam, "A gaseous core fission reactor with autonomously oscillating fuel gas", Fusion Technology, Vol. 20, No. 4, Part 2, December 1991, 545 - 549.
J.C. Kuijper & H., van Dam, "Thermodynamic cycle calculations for a pumped gaseous core fission reactor", Journal of Nuclear Science and Technology, Vol. 28, No. 2, January 1991, 95 – 106.
J.C. Kuijper et al., "Reactor physics and thermodynamics of a gaseous core fission reactor", Proc. PHYSOR-90, P III, 1990, 157 - 166.
J.C. Kuijper et al., "Simulator studies of a gaseous core fission reactor", Proc. 5th International Conference on Emerging Nuclear Energy Systems, Singapore Science Publishers, 1989, 51 - 55.