One of the challenges that today's new workforce of nuclear criticality safety engineers face is the opportunity to provide assessment of nuclear systems and establish safety guidelines without having received significant experience or hands-on training prior to graduation. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and/or the International Reactor Physics Experiment Evaluation Project (IRPhEP) provides students and young professionals the opportunity to gain experience and enhance critical engineering skills

Bess, John D.

Briggs, J. Blair

Nigg, David W.

UNT Digital Library

  This is a preprint of a paper intended for publication in a journal or proceedings. Since changes may be made before publication, this preprint should not be cited or reproduced without permission of the author. This document was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party’s use, or the results of such use, of any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights. The views expressed in this paper are not necessarily those of the United States Government or the sponsoring agency. INL/CON-09-16338PREPRINTProviding Nuclear Criticality Safety Analysis Education Through Benchmark Experiment Evaluation  2009 Young Professionals Congress at the American Nuclear Society 2009 Winter Meeting  John D. Bess J. Blair Briggs David W. Nigg  November 2009  Providing Nuclear Criticality Safety Analysis Education through Benchmark Experiment Evaluation John D. Bess J. Blair Briggs David W. Nigg Idaho National Laboratory, P.O. Box 1625, MS 3855, Idaho Falls, Idaho, 83415-3855 John.Bess@inl.gov, J.Briggs@inl.gov, David.Nigg@INL.gov INTRODUCTIONOne of the challenges that today’s new workforce of nuclear criticality safety engineers face is the opportunity to provide assessment of nuclear systems and establish safety guidelines without having received significant experience or hands-on training prior to graduation.  Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and/or the International Reactor Physics Experiment Evaluation Project (IRPhEP) provides students and young professionals the opportunity to gain experience and enhance critical engineering skills. DESCRIPTION OF THE ACTUAL WORK Both the ICSBEP and IRPhEP publish new editions of their respective benchmark handbooks each year that contain an ever-growing collection of collaborative international evaluations.  The September 2009 edition of the ICSBEP Handbook1 contains approximately 4,295 critical or subcritical benchmark configurations, twenty-four criticality-alarm/shielding benchmark configurations, and 200 fundamental physics benchmark quantities representing efforts from 20 contributing countries.  The March 2009 edition of the IRPhEP Handbook2 provides benchmarks from 36 experimental series from 21 reactor facilities representing efforts from 15 contributing countries. Benchmark procedures require the student to investigate the background, methods, and results of the experiment being evaluated.  Often experiments were performed with the intention to provide data for safety assessments and may have been subsequently utilized in the development of criticality safety standards.  When possible, the original experimenters are contacted to clarify published documentation.   Additional research and often engineering judgment is required when an evaluator must assess incomplete or misleading experimental information throughout the course of the benchmark evaluation.  Members of the ICSBEP and IRPhEP team, as well as other laboratory or institute personnel provide their expertise in developing an in-depth evaluation.  The skills, tools, and network development established during this experience is of great benefit to students returning to their universities and young professional engineers entering the workforce. The evaluator must also develop and analyze computational models of the experiment to assess uncertainty in the benchmark and provide benchmark specifications.  Each evaluation report must undergo a thorough review by experienced staff with the evaluator’s organization. The internal reviewer will often provide additional guidance prior to submission to an independent review from the international criticality safety, nuclear data, or reactor physics communities.   Once the independent review is completed and all concerns resolved, each evaluation report is submitted to the respective ICSBEP or IRPhEP Technical Review Group for review prior to the annual meeting.  Each Technical Review Group is comprised of 30 to 40 experts from the international community.  Evaluation reports that are proposed for publication in the ICSBEP or IRPhEP Handbooks are each discussed in detail at the Technical Review Meeting.  Review group comments must be resolved prior to prior to publication in the respective Handbook.  Evaluators are also encouraged to submit their activities for a presentation at professional conferences. Student and young professional participation in the benchmark process is of benefit to the ICSBEP and IRPhEP, the various international user communities, the professional development of the individual, and ultimately, the company or laboratory at which the individual finds employment. RESULTSNational laboratory, institute, university and industry participation in the ICSBEP and IRPhEP has provided benchmark research and evaluation experience to at least 30 students since 1995.  Over that period students have authored or coauthored 51 ICSBEP or IRPhEP evaluations and several technical papers for various conferences and journals. A summary of student contributions to the ICSBEP and IRPhEP is given in Table 1. ACKNOWLEDGMENTS The ICSBEP and IRPhEP are collaborative efforts that involve numerous scientists, engineers, administrative support personnel, and program sponsors from 22 different countries.  The authors would like to Next Generation of Nuclear Criticality Safety Professionals 1117acknowledge the efforts of all of these dedicated individuals without whom the ICSBEP and IRPhEP would not be possible.  This paper was prepared at Idaho National Laboratory for the U.S. Department of Energy under Contract Number (DE-AC07-05ID14517). REFERENCES  1. International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)03, OECD-NEA (2009). 2. International Handbook of Evaluated Reactor Physics Benchmark Experiments,NEA/NSC/DOC(2006)1, OECD-NEA, March (2009).Table 1.  Summary of Student Contributions1 to the ICSBEP and IRPhEP EVALUATION ID & TITLE (YEAR APPROVED)AUTHOR2(University)NATIONAL  LABORATORYor COMPANY3HEU-MET-FAST-007 – Uranium Metal Slabs Moderated with Polyethylene, Plexiglas, and Teflon (1995)Catherine Crawford (North Western University)INLHEU-SOL-THERM-006 – Experiments with Boron-Poisoned Highly Enriched Uranyl Nitrate Solution (1997) Catherine Crawford (North Western University) INLU233-SOL-THERM-012 – Water-Reflected Spherical Vessels Partially Filled or Filled with 233UO2(NO3)2 Solution (2002) Paul Foster (Brigham Young University) INLU233-SOL-THERM-013 – Unreflected Spherical Vessels Partially Filled or Filled with 233UO2(NO3)2 Solution (2003) Paul Foster (Brigham Young University) INLMIX-MISC-THERM-004 – Water-Reflected Triangular-Pitched Lattice of Mixed Oxide Fuel Rods Immersed in Plutonium / Uranyl Nitrate Solution Containing Gadolinium (2003) Paul Foster (Brigham Young University) INLMIX-SOL-THERM-007 – Water-Reflected Plutonium-Uranyl Nitrate Solution Containing Gadolinium (2004) Wade Butaud (Texas A&M University) INLHEU-SOL-THERM-050 – Unreflected Aluminum Cylinders Containing Uranyl Fluoride Solutions (2005) Wade Butaud (Texas A&M University) INLHEU-MET-FAST-076 – Uranium (93.14 235U) Metal Annuli and Cylinders with Thick Polyethylene Reflectors and/or Internal Polyethylene Moderator (2006) Tyler Sumner (Georgia Institute of Technology) INLHEU-MET-FAST-084 – HEU Metal Cylinders with Magnesium, Titanium, Aluminum, Graphite, Mild Steel, Nickel, Copper, Cobalt, Molybdenum, Natural Uranium, Tungsten, Beryllium, Aluminum Oxide, Molybdenum Carbide, and Polyethylene Reflectors (2007) Bernard Jones (Georgia Institute of Technology) INLHEU-MET-FAST-085 – Highly Enriched Uranium Metal Spheres Surrounded by Copper, Cast Iron, Nickel, Nickel-Copper-Zinc Alloy, Thorium, Tungsten Alloy, or Zinc Reflectors (2007) Jessica Feener (Georgia Institute of Technology) INLPU-MET-FAST-042 – Plutonium Hemispheres Reflected by Steel and Oil (2008) John D. Bess (University of Utah) INLLEU-COMP-THERM-028 – Water-Moderated U(4.31)O2 Fuel Rods In Triangular Lattices with Boron, Cadmium and Gadolinium as Soluble Poisons (2008) Jose Ignacio Marquez Damian (Georgia Institute of Technology) INLLEU-MISC-THERM-004 – U(4.31)O2 Fuel Rods In Uranyl Nitrate Solution Containing Gadolinium (2008) Jose Ignacio Marquez Damian (Georgia Institute of Technology) INLIEU-COMP-THERM-012 – RA-0 Reactor: Graphite Reflected Arrangement of UO2-Graphite Fuel Rods in Water (2008) Jose Ignacio Marquez Damian (Instituto Balseiro - Universidad Nacional de Cuyo) INL                                                          1 The author’s intent is to include all student contributions and extend an apology to any who have inadvertently not been included. 2 Only student authors are listed.  Many evaluation reports include other authors the names of whom may be found in References 1 and 2. 3 INL – Idaho National Laboratory, WSMS – Washington Safety Management Solutions under subcontract to the INL, ORNL – Oak Ridge National Laboratory, ANL – Argonne National Laboratory, LLNL – Lawrence Livermore National Laboratory, JSI – Jozef Stefan Institute IPPE – Institute of Physics and Power Engineering, NNL – National Nuclear Laboratory.Next Generation of Nuclear Criticality Safety Professionals1118EVALUATION ID & TITLE (YEAR APPROVED)AUTHOR2(University)NATIONAL  LABORATORYor COMPANY3IEU-COMP-THERM-009 – Power Burst Facility:  U(18)O2-CaO-ZrO2Fuel Rods in Water (2009) Jose Ignacio Marquez Damian Alexis Weir (Instituto Balseiro - Universidad Nacional de Cuyo) INLHEU-SOL-THERM-026 – Highly Enriched Uranyl Nitrate in Annular Tanks with Concrete Reflection: 1 × 3 Line Array of Nested Pairs of Tanks (2009) James Cleaver (Idaho State University) INLFFTF-LMFR-RESR-001 – Evaluation of the Initial Isothermal Physics Measurements on the Fast Flux Test Facility, A Prototypic Liquid Metal Fast Breeder Reactor (TBD) John D. Bess (University of Utah) INLHEU-SOL-THERM-034 – Water-Moderated and -Reflected Slabs of Uranium Oxyfluoride (TBD) Margaret A. Marshall (University of Utah) INLHEU-MET-FAST-054 – Concrete Reflected Arrays of Highly Enriched Uranium Cylinders (TBD) Mackenzie L. Gorham (Idaho State University) INLHEU-SOL-THERM-009 – Water-Reflected 6.4-Liter Spheres of Enriched Uranium Oxyfluoride Solutions (1996) Michelle Pitts (Georgia Institute of Technology) WSMS HEU-SOL-THERM-010 – Water-Reflected 9.7 Liter Spheres of Enriched Uranium Oxyfluoride Solutions (1996) Michelle Pitts (Georgia Institute of Technology) WSMS HEU-SOL-THERM-011 – Water-Reflected 17 Liter Spheres of Enriched Uranium Oxyfluoride Solutions (1996) Michelle Pitts (Georgia Institute of Technology) WSMS HEU-SOL-THERM-012 – Water-Reflected 91-Liter Sphere Of Enriched Uranium Oxyfluoride Solution (1996) Michelle Pitts (Georgia Institute of Technology) WSMS HEU-SOL-THERM-013 – Unreflected 174-Liter Spheres Of Enriched Uranium Nitrate Solutions (1996) Michelle Pitts (Georgia Institute of Technology) WSMS LEU-SOL-THERM-002 – 174 Liter Spheres Of Low Enriched (4.9%) Uranium Oxyfluoride Solutions (1997) Michelle Pitts (Georgia Institute of Technology) WSMS PU-MET-FAST-016 – Flooded 3x3x3 Arrays of 3-Kg Plutonium Metal Cylinders - Phase 1 (1997) Michelle Pitts (Georgia Institute of Technology) WSMS PU-MET-FAST-037 – Flooded 2x2xN Arrays of 3-Kg Plutonium Metal Cylinders - Phase 2 (1998) Michelle Pitts (Georgia Institute of Technology) WSMS MIX-COMP-THERM-005 – Water-Moderated Mixed Plutonium-Uranium Oxide Pins, 4.0 Wt.% PuO2, 18% 240Pu, Natural Uranium (1999)Darby S. Kimball (University of Virginia) WSMS MIX-COMP-THERM-006 – Water-Moderated Mixed Oxide Hexagonal Lattices - 2.0 Wt.% PuO2, 8% 240Pu, Natural Uranium (2000) Jim W. Campbell (Georgia Institute of Technology) WSMS HEU-MET-FAST-078 – HEU Metal Cylinders, Partially Reflected by Water, Polyethylene, Lucite, and Paraffin (2006) Nick Schira (University of Cincinnati) WSMS PU-SOL-THERM-018 – Water-Reflected 24-Inch Diameter Cylinder of Plutonium (42.9% 240Pu) Nitrate Solution (2006) Doug Warner (University of Cincinnati) WSMS PU-SOL-THERM-034 – Plutonium (8.3 Wt.% 240Pu) Nitrate Solution With Gadolinium In Water-Reflected 24-Inch Diameter Cylinder (2007) Nick Schira Kyle Knecht (University of Cincinnati) WSMS HEU-MET-FAST-051 – Uranium (93.2) Metal Cylinders (7-Inch, 9-Inch, 11-Inch, 13-Inch, and 15-Inch Diameter) and Two 11-Inch-Diameter Interacting Uranium (93.2) Metal Cylinders (2002) Robert H. Elwood, Jr. (University of Tennessee - Knoxville) ORNLU233-SOL-THERM-016 – Unreflected Solutions of 233UO2(NO3)2 in Cylinders (2005) Shane E. Parkey (University of Tennessee - Knoxville) ORNLU233-SOL-THERM-017 – Water-Reflected Solutions of  233UO2(NO3)2in Cylinders (2005) Shane E. Parkey (University of Tennessee - Knoxville) ORNLLEU-MET-THERM-007  – Water-Moderated and Water-Reflected 0.300 Inch Diameter U(4.95) Metal Rods in 1.3, 1.53, 1.8, 2.05, 2.453 and 2.9 Cm Square-Pitched Arrays (TBD) Carlos H. Juarez-Gosselin (University of Tennessee - Knoxville) ORNLNext Generation of Nuclear Criticality Safety Professionals 1119EVALUATION ID & TITLE (YEAR APPROVED)AUTHOR2(University)NATIONAL  LABORATORYor COMPANY3MIX-COMP-FAST-001 – ZPR-6 Assembly 7:  A Cylindrical Assembly with Mixed (Pu,U)-Oxide Fuel and Sodium with a Thick Depleted-Uranium Reflector (2003) Pedro Moneo, Paul A. Van den Hende (Institut National des Sciences et Techniques Nucléaires) ANLHEU-MET-FAST-057 – Highly Enriched Uranium Metal Spheres and Cylinders Reflected by Lead (2004) Mark Lee (University of California – Berkeley) LLNL MIX-MISC-THERM-005 – Water-Reflected Triangular-Pitched Lattice of Mixed Oxide Fuel Rods Immersed in Plutonium-Uranyl Nitrate Solution Containing Boron and Gadolinium (2005) Milan Tomazin University of Ljubljana JSI MIX-SOL-THERM-010 – Water-Reflected Plutonium-Uranyl Nitrate Solution Containing Boron and Gadolinium (2006) Milan Tomazin Luka Snoj University of Ljubljana JSI LEU-COMP-THERM-081 – PWR Type UO2 Fuel Rods with Enrichments of 3.5 and 6.6 Wt.% with Burnable Absorber  (“Otto Hahn” Nuclear Ship Program, Second Core) (2007) Petra Rogan Luka Snoj University of Ljubljana JSI KRITZ-LWR-RESR-001 – KRITZ-2:19 Experiment on Regular H2O/Fuel Pin Lattices with Mixed Oxide Fuel at Temperatures 21.1 and 235.9 °C (2009) Luka Snoj University of Ljubljana JSI KRITZ-LWR-RESR-002 – KRITZ-2:1 Experiment on Regular H2O/Fuel Pin Lattices with Low Enriched Uranium Fuel at Temperatures 19.7 °C and 248.5 °C (2009) Luka Snoj University of Ljubljana JSI KRITZ-LWR-RESR-003 – KRITZ-2:13 Experiment on Regular H2O/Fuel Pin Lattices with Low Enriched Uranium Fuel at Temperatures 22.1 °C and 243 °C (2009) Luka Snoj University of Ljubljana JSI HEU-MET-THERM-032 – 1x1 HEU/Polyethylene Reflected and Moderated by Polyethylene (TBD) Luka Snoj Gasper Zerovnik University of Ljubljana JSI BFS1-FUND-EXP-001 – BFS-97, -99, -101 Assemblies: ExperimentalProgram on Critical Assemblies with Heterogeneous Compositions of  Plutonium, Depleted-Uranium Dioxide, and Polyethylene (2007) Olga Pavlova (Institute of Atomic Power Engineering) IPPE BFS1-FUND-EXP-002 – Experimental Program Performed at the BFS-42Assembly – K-Infinity Experiments for 238U in Fast Neutron Spectra:  Measurements with Plutonium Mixed with Depleted Uranium  Dioxide and Polyethylene (2007) Olga Pavlova (Institute of Atomic Power Engineering) IPPE BFS2-FUND-EXP-001 – Experimental Program Performed at the BFS-31Assemblies – K-Infinity Experiments for 238U in Fast Neutron Spectra:  Measurements with Plutonium Mixed with Depleted Uranium Dioxide (200Olga Pavlova (Institute of Atomic Power Engineering) IPPE BFS1-FUND-EXP-003 – BFS-57 And BFS-59 Assemblies: Experimental Program on Critical Assemblies with Heterogeneous Compositions of Enriched-Uranium Dioxide or Plutonium, Depleted-UraniumDioxide, and Polyethylene (2008) Olga Pavlova (Institute of Atomic Power Engineering) IPPE FUND-JINR-1/E-MULT-TRANS-001 – Neutron Transmission Through Samples of Depleted Uranium, Highly – Enriched Uranium, and Plutoniumfor Determination of Resonance Self-Shielding of Total Cross Section and Fission Cross Section of 238U, 235U, and 239Pu (2008) Olga Pavlova (Institute of Atomic Power Engineering) IPPE VENUS-PWR-EXP-005 – Experimental Study of the VENUS-PRP  Configurations No. 9 and  9/1 (TBD) Christopher Grove (Birmingham University-UK) NNLNext Generation of Nuclear Criticality Safety Professionals1120

Providing Nuclear Criticality Safety Analysis Education through Benchmark Experiment Evaluation

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Providing Nuclear Criticality Safety Analysis Education through Benchmark Experiment Evaluation

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