Meetings

ANS NCSD 2013 Topical Meeting
Wilmington, NC • Sep 29 – Oct 3, 2013
Monday September 30 Opening Plenary
The Role of Administration in Nuclear Criticality Safety
Calvin Hopper, Honorary Chair
An Historical Perspective of Nuclear Criticality Safety
Richard Malenfant, Plenary Speaker
Monday, Sept. 30
Methods I
Fission Matrix Capability for MCNP
Forrest B. Brown (1), Sean E. Carney (2), Brian C. Kiedrowski (1), William R. Martin (2)
1) Monte Carlo Codes Group, Los Alamos National Laboratory, Los Alamos NM, 2) NERS Department, University of Michigan, Ann Arbor, MI
Verification of MCNP5-1.60 and MCNP6.1 for Criticality Safety Applications
Forrest B. Brown, Brian C. Kiedrowski, Jeffrey S. Bull
Monte Carlo Codes Group, Los Alamos National Laboratory, Los Alamos NM
Status of MCNP Sensitivity/Uncertainty Capabilities for Criticality
Brian C. Kiedrowski, Albert C. Kahler, III, and Michael E. Rising
Los Alamos National Laboratory, Los Alamos, NM
Determination of Correlations among Benchmark Experiments by Monte Carlo Sampling Techniques
Matthias Bock and Maik Stuke
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, München, Germany
Impact of Correlated Benchmark Experiments on the Computational Bias in Criticality Safety Assessment
Matthias Bock and Matthias Behler
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, München, Germany
Trends of the deterministic route APOLLO2.8/JEFF-3.1.1 of CRISTAL V2 Criticality Package in ICSBEP benchmarks
C. Riffard, C. Carmouze and A. Santamarina (1), G. Grassi (2)
1) Commissariat à l’Énergie Atomique et aux Énergies Alternatives, CEA, DEN, DER, SPRC, Saint-Paul-lez-Durance, France, 2) AREVA NC, Paris La Défense, France
Feedback on nuclear data for separated Burnup fission products oscillations in the MINERVE reactor with JEFF-3 library in PWR-MOx fuel criticality-safety studies
A. Chambon, A. Santamarina, G. Noguère and C. Riffard (1), F. Lavaud and D. Lecarpentier (2)
1) CEA, DEN, DER, SPRC, Cadarache Center, Saint Paul-lez-Durance, France, 2) EDF, Clamart, France
Innovative Method to Calculate the Atomic Densities of any Compound Mixed with a Moderator
D. Noyelles, F.X. Giffard and E. Gagnier
Commissariat à l’Énergie Atomique et aux Énergies Alternatives – Centre de Saclay, DEN/DANS/DM2S/SERMA, Gif sur Yvette Cedex,France
Hybrid Technique in SCALE for Fission Source Convergence Applied to Used Nuclear Fuel Analysis
A.M. Ibrahim, D.E. Peplow, K.B. Bekar, C. Celik, J.M. Scaglione, D. Ilas, J.C. Wagner
Oak Ridge National Laboratory, Oak Ridge, TN
Criticality Safety Demonstration Using Low Fissile Concentration in Waste
A. Coulaud, G. Néron de Surgy (1), E. Guillou (2), L. Cholvy (3)
1) AREVA E&P, Montingy-le-Bretonneux, France, 2) AREVA NC La Hague, Beaumont-Hague Cedex, France, 3) CEA Marcoule, Bagnols sur Cèze, France
Analysis & Experiments I
Exclusion of Criticality for a Final Repository in a Saline Host Rock based on the Neutron Absorbing Properties of Cl-35
Robert Kilger, Matthias Bock, and Bernhard Gmal
Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Munich, Germany
Safety Analyses for Solid Fuel Thorium Molten Salt Reactor (SFTMSR) Core Replacement (not presented)
Zhaozhong HE, and Kun CHEN (1), Guoshun YOU and Jianping JING (2)
1) Center for Thorium Molten Salt Reactor (TMSR) Research, Shanghai Institute of Applied, Physics (SINAP), Chinese Academy of
Sciences (CAS), Shanghai, China, 2) Nuclear and Radiation Safety Centre, Ministry of Environmental Protection of the People’s Republic
of China, Beijing, China
Above 5% 235U enrichment – A new AREVA challenge for criticality safety assessments in an UO2 fuel fabrication plant
N. Comte And M. Doucet (1), M. Manhes (2), P. Bouvet (3)
1) AREVA – AREVA NP Fuel Business Unit, Lyon, France, 2) 2011 Internship in the frame of a Master Degree Graduation, 3) AREVA –
FBFC, Romans sur Isère, France
Reevaluation of the Jezebel Benchmark: Assumptions About Masses and Dimensions
Jeffrey A. Favorite and Roger W. Brewer (1), Raymond L. Reed (2)
1) X-Computational Physics Division, Los Alamos National Laboratory, Los Alamos, NM, 2) URS Professional Solutions LLC, Aiken, SC
Uranium Conservative Modeling: Homogeneous or Heterogeneous Fissile Medium?
D. Noyelles And E. Gagnier
Commissariat à l’Énergie Atomique et aux Énergies Alternatives – Centre de Saclay, DEN/DANS/DM2S/SERMA, Gif sur Yvette Cedex, France
The ORSphere Benchmark Evaluation and Its Potential Impact on Nuclear Criticality Safety
John D. Bess, Margaret A. Marshall, and J. Blair Briggs
Idaho National Laboratory, Idaho Falls, ID
Additions to the ICSBEP and IRPhEP Handbooks Since NCSD 2009
John D. Bess and J. Blair Briggs (1), Jim Gulliford and Ian Hill (2)
1) Idaho National Laboratory, Idaho Falls, ID, 2) Organization for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA), Paris, France
Interspersed Moderation, What is Credible?
Larry L. Wetzel, P. E., Brandon M. O’Donnell, Daniel L. Ashworth
Babcock & Wilcox Nuclear Operations Group, Inc., Lynchburg, VA
Full Burnup Credit Conservatisms in PWR-UOx Industrial Applications, due to the Correction and Penalty Factors Derived from the French Experiments using the JEFF3.1.1 Evaluation
C. Carmouze, C. Riffard, A. Santamarina (1), G. Grassi (2)
1) Commissariat à l’Énergie Atomique et aux Énergies alternatives, CEA, DEN, DER, SPRC, Saint-Paul-lez-Durance, France, 2) AREVANC, Paris La Défense, France
Validation of 108 MOX Powder Applications for ANS and ISO Standards
Dennis Mennerdahl
E Mennerdahl Systems, Täby, Sweden
Use of Gadolinium as a Criticality Safety Control in Fuel Fabrication Process
David Eghbali
GE Hitachi Nuclear Energy, Wilmington, NC
Sub-critical Mass Determination for Cylindrical Systems of U-235, U-233 and Pu-239
Nhu-Thuy Tran and Eugene Masala
Atomic Energy of Canada Limited (AECL) – Chalk River Laboratories, Ontario, Canada
Tuesday October 1
Methods II
Use of Tsunami in validation of Scale 6.1 for the Swedish spent fuel repository – Selection of experiments
Fredrik Johansson and Henrik Liljenfeldt
Swedish Nuclear Fuel and Waste Management Co (SKB), Stockholm, Sweden
The Development and V&V of the Transport Module Based on MOC Method in Lattice Code LATC
Li Shuo, Chen Yixue, Yu Hui, Liu Zhiyan, Yan Yuhang
State Nuclear Power Software Development Center, Xicheng District, Beijing, China
Calculating Alpha-eigenvalue Spectra with Monte Carlo
Benjamin R. Betzler (1), Brian C. Kiedrowski and Forrest B. Brown (2), William R. Martin (3)
1) University of Michigan, Ann Arbor, MI, 2) Los Alamos National Laboratory, Los Alamos, NM, 3) University of Michigan, Ann Arbor, MI
Importance of Scattering Distributions on Criticality
Brian C. Kiedrowski
Los Alamos National Laboratory, Los Alamos, NM
Comparison of Validation Results for GEMER, MCNP, and SCALE/KENO-VI
David Eghbali, Qi Ao and John Hannah
GE Hitachi Nuclear Energy, Wilmington, NC
Use of SCALE Continuous-Energy Monte Carlo Tools for Eigenvalue Sensitivity Coefficient Calculations
Christopher M. Perfetti and Bradley T. Rearden
Oak Ridge National Laboratory, Oak Ridge, TN
Recycling Facility Periodic Safety Review: A Methodology Used for the Nuclear Criticality Safety Review Of Geometrically Safe or Favorable Equipment
M. Hampartzounian, Y. Blin, A. Coulaud, G. Néron de Surgy and A. Bardelay (1), E. Guillou (2), G. Grassi (3)
1) AREVA E&P, Montingy-le-Bretonneux, France, 2) AREVA NC, Beaumont-Hague Cedex, France, 3) AREVA NC, Paris La Défense Cedex, France
The SCALE Verified, Archived Library of Inputs and Data – VALID
W.J. Marshall and B.T. Rearden
Oak Ridge National Laboratory, Oak Ridge, TN
Benefits of Using EPRI Depletion Reactivity Benchmarks for Burnup Credit Validation
Dale B. Lancaster (1), K. S. Smith (2), A. J. Machiels (3)
1) NuclearConsultants.com, Boalsburg, PA, 2) Department of Nuclear Engineering, Cambridge, MA, 3) Electric Power Research Institute,Inc., Palo Alto, CA
Analysis & Experiments
Evaluation of the Kyoto University Critical Assembly Erbium Oxide Experiments
Joseph A. Christensen
U.S. Department of Energy – Idaho Operations Office, Idaho Falls, ID
EPRI Depletion Benchmark Calculations Using PARAGON
Vefa N. Kucukboyaci
Westinghouse Electric Company, LLC, Cranberry Woods, PA
Validation of Critical Parameter Calculations for Sodium Diuranate using Sensitivity and Uncertainty Analysis
Philip Sewell and Peter Vescovi
DAHER-TLI, Columbia, SC
Measurement and Modeling of Void Effects on Multiplication in a Homogeneous Thermal Reactor
Robert D. Busch
University of New Mexico, Chemical and Nuclear Engineering Department, Albuquerque, NM
Credible Moderation Content of Uranium Oxide Powder and Pellet Systems
Elisabeth Dunn, Steven Brown, Mark Dodds, Alison Thomas
Global Nuclear Fuels – America (GNF-A), Wilmington, NC
Effects of Particle Size and Density on UO2 Systems
Elisabeth Dunn and David Eghbali
Global Nuclear Fuels – America (GNF-A), Wilmington, NC
Production of a Criticality Safety Case for Reprocessing Enriched Material Through the MAGNOX Reprocessing Plant at Sellafield
D Ellis, S Hollman, D McCrindle and G Palmer
Sellafield Ltd, Seascale, CA20 1PG, United Kingdom
Results of Critical Experiments on Water-Moderated Fully-Reflected 6.90% Enriched UO2 Fuel Pin Arrays with a Fuel-to-Water Volume Ratio of 0.52
Gary A. Harms, Allison D. Miller, and John T. Ford
Sandia National Laboratories, Albuquerque, NM
Justification to Disregard U-234 Mass in Certain Uranium Systems
Andrew R. Wysong
Lawrence Livermore National Laboratory, Livermore, CA
Conference Banquet
GE Hitachi Nuclear Energy – Raising the Bar
Kevin Walsh, General Chair
Senior Vice President
Nuclear Fuels & Services, GE Hitachi Nuclear Energy
Wednesday October 2
Programs / Training / Risk Assessment / Post-Fukushima
Generic Criticality Considerations for Spent Fuel Pool Storage Racks under Beyond Design Basis Accident Conditions
Robert Kilger, Matthias Bock, and Bernhard Gmal
Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Munich
The Official Website of the U.S. Department of Energy’s Nuclear Criticality Safety Program
Brian L. Koponen, David P. Heinrichs, Chuck K. Lee (1), Lori Scott (2)
1) Lawrence Livermore National Laboratory, Livermore CA, 2) SAIC, Solana Beach, CA
Evolution of Nuclear Criticality Safety Training at Atomic Energy of Canada Ltd. to Meet its Changing Needs
David Pilgrim
Atomic Energy of Canada Limited, Chalk River, ON, Canada
Evidence of a Criticality Accident Occurring with Spent Fuels: Basic Considerations and Lessons Learned from the Fukushima Accident
M. Duluc, G. Caplin And W. Haeck
Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Fontenay-aux-Roses Cedex, FRANCE
Development and Implementing Online Nuclear Criticality Safety
Training and Education
Charlotta E. Sanders and Kevin L. Wilcoxon
University of Nevada, Las Vegas, NV
Uncertainty Evaluation of Reactivity for Long-term Dry Cask Storage
Jeremiah Boles, Aaron McGee, Quentin Newell, Charlotta Sanders
Department of Mechanical Engineering, University of Nevada, Las Vegas, Nevada
Multidisciplinary Assessment of Firefighting
B. Webborn
Sellafield Ltd, Seascale, CA20 1PG, United Kingdom
The Horizontal Band Saw Incident at Babcock & Wilcox, NOG-L
Larry L. Wetzel
Babcock & Wilcox Nuclear Operations Group, Inc., Lynchburg, VA
NCS Approach for Decommissioning of Low and Intermediate Level Waste Soils and Process Piping Using the InSpector 1000 with LaBr
Megan Pritchard
Nuclear Safety Associates, Charlotte, NC
Los Alamos National Laboratory Criticality Safety Boot Camp – Rebuilding the Core
David Solms (1), Fitz Trumble (2)
1) Los Alamos National Laboratory, 2) URS Professional Solutions, Aiken, SC
Current Status of the DOE Nuclear Criticality Safety Program Hands-On Criticality Safety Training Course at Sandia
Gary A. Harms, Ronald A. Knief, Allison D. Miller, and John T. Ford
Sandia National Laboratories, Albuquerque, NM
Accidents and Response
Methodology to Determine Requirements for Installation of Criticality Accident Alarm Systems
J. Wang and C. McNally
Atomic Energy of Canada Limited – Chalk River Laboratories, , Chalk River, ON, Canada
Analysis of Measured Data From Experiments 2 and 3 of the 2010 Criticality Accident Alarm System Benchmark at the CEA Valduc Silene Facility
T. M. Miller, M. E. Dunn, J. C. Wagner, and K. L. McMahan (1), N. Authier, X. Jacquet, G. Rousseau, H. Wolff, J. Piot, L.
Savanier, and N. Baclet (2), Y.-K. Lee, V. Masse1, J.-C. Trama, E. Gagnier, S. Naury, and P. Blanc-Tranchant (3), R. Hunter (4), S. Kim and G. M. Dulik (5), K. H. Reynolds (6)
1) Oak Ridge National Laboratory, Oak Ridge, TN, 2) Commissariat à l’Énergie Atomique et aux Énergies Alternatives —Centre de Valduc, Is sur Tille, France, 3) Commissariat à l’Énergie Atomique et aux Énergies Alternatives —Centre de Saclay, Gif sur Yvette Cedex, France, 4) Babcock International Group, Warrington, England, 5) Lawrence Livermore National Laboratory, Livermore, CA, 6) Y-12 National
Methodology to Assess Minimum Accident of Concern and Criticality Accident Alarm System Location
R. Dranga and J. Wang
Atomic Energy of Canada Limited – Chalk River Laboratories, Chalk River, ON, Canada
Guidance Detailing Methods to Calculate Criticality Accident Alarm System Detector Response and Coverage
T. M. Miller and D. E. Peplow
Oak Ridge National Laboratory, Oak Ridge, TN
Sensitivity and Uncertainty Analysis of a Fixed Source Criticality Accident Alarm System Benchmark Experiment
Kevin H. Reynolds (1), Thomas M. Miller (2), Laurence F. Miller (3)
1) Y-12 National Security Complex, Oak Ridge, TN, 2) Oak Ridge National Laboratory, Oak Ridge, TN, 3) University of Tennessee
Knoxville, Knoxville, TN
The Development of a New Criticality Accident Alarm System
Richard Hunter (1), Russell King, Philip Bodman and Kevin Freer (2)
1) Babcock International Group, Warrington, Cheshire, England, 2) Babcock International Group, Seascale, Cumbria, England
Radiation Tolerance Assessment of a Criticality Accident Alarm System
Richard Hunter (1), Russell King, Philip Bodman and Kevin Freer (2)
1) Babcock International Group, Warrington, Cheshire, England, 2) Babcock International Group, Seascale, Cumbria, England
Designed to Address Operational Gain
P. Blot, P. Chaudun, N. Menaa (1), J. Handley, J.M. Kirkpatrick, S. Philips (2), R. Abou Khalil (3)
1) AREVA/Business Unit Nuclear Measurements – CANBERRA, Saint-Quentin-en-Yvelines, France, 2) CANBERRA, Meriden, CT, 3) AREVA/DRD – Research and Development, 3) PARIS La Defense, France
Criticality Accident Alarm System Detector Placement Methodology at the GNF-A Fuel Manufacturing Operations Facilities
Christopher A. Geiser, Qi Ao, and John F. Zino
GE Hitachi Nuclear Energy, Wilmington, NC
On the Kinetics of Critical Excursions Pertinent to the ANS-8.3 Minimum Accident – A Focus on the ‘Rapid Transient’
Peter L. Angelo, Jason J. McCall, Ronald T. Nore
Y-12 National Security Complex, Oak Ridge, TN
Proposed Guidance and Specification for a Process-Specific Minimum Accident of Concern
Peter L. Angelo
Y-12 National Security Complex, Oak Ridge, TN
Thursday, October 3
Methods III
Fission Products Credit for PWR MOX Burnup Credit Implementation
Ludyvine Jutier and Stéphane Evo (1), Eric Guillou (2), Gabriele Grassi (3)
1) Institut de Radioprotection et de Sûreté Nucléaire, Fontenay-aux-Roses Cedex, FRANCE, 2) AREVA, Beaumont Hague, FRANCE, 3)
AREVA, BU Recycling, Paris La Défense, FRANCE
Criticality Safety Calculation Package for Fuel Transport and Storage Systems
K.M. Rantamäki
VTT Technical Research Centre of Finland, VTT, Finland
On the Assumption of the Maximum Void Fraction in Burnup Credit Implementation for BWR Fuel
Ludyvine Jutier, Stéphane Evo and Grégory Caplin (1), Gabriele Grassi (2)
1) Institut de Radioprotection et de Sûreté Nucléaire, Fontenay-aux-Roses Cedex, FRANCE, 2) AREVA, BU Recycling, Paris La Défense,FRANCE
Quantification of Uncertainties and Correlations in Criticality Experiments with SCALE
Bradley T. Rearden (1), Kevin J. Dugan (2), František Havlůj (3)
1) Oak Ridge National Laboratory, Oak Ridge, TN, 2) Department of Nuclear Engineering Texas A&M University, College Station, TX, 3)
Nuclear Research Institute at Rez Husinec – Řež, Hlavní, Czech Republic
The Use of the Density-Law-Invariant Parameters for Criticality Safety Assessment
Song T. Huang and Philip Chou
Lawrence Livermore National Laboratory, Livermore, CA
Enhancements in Continuous-Energy Monte Carlo Capabilities in SCALE
K. B. Bekar, C. Celik, D. Wiarda, D. E. Peplow, B. T. Rearden, and M. E. Dunn
Oak Ridge National Laboratory, Oak Ridge, TN
Validation of Criticality Safety Calculations with SCALE 6.2
W. J. Marshall, D. Wiarda, C. Celik, and B. T. Rearden (1), D. R. Wentz (2)
1) Oak Ridge National Laboratory, Oak Ridge, TN, 2) University of Tennessee-Knoxville, Knoxville, TN
Validation of SCALE 6.1 at Spectra Tech Inc.
D. F. Hollenbach and K. E. Hollenbach and R. G. Taylor
Spectra Tech, Inc., Oak Ridge, TN
Comparison of Burnup Credit Uncertainty Quantification Methods
W. A. Wieselquist, K. S. Kim, G. Ilas, and I. C. Gauld
Oak Ridge National Laboratory, Oak Ridge, TN
Overview of SCALE 6.2
B. T. Rearden, M. E. Dunn, D. Wiarda, C. Celik, K. Bekar, M. L. Williams, D. E. Peplow, C. M. Perfetti, I. C. Gauld, W. A. Wieselquist, J. P. Lefebvre, and R. A. Lefebvre (1), F. Havlůj (2), S. E. Skutnik (3), K. J. Dugan (4)
1) Oak Ridge National Laboratory, Oak Ridge, TN, 2) Nuclear Research Institute at Řež, Hlavní, Czech Republic, 3) University of
Tennessee, Knoxville, TN, 4) Texas A&M University, College Station, TX
SCALE Uncertainty Quantification Methodology for Criticality Safety Analysis of Used Nuclear Fuel
M. L. Williams, F. Havluj, D. Wiarda, M. Pigni, I. Gauld
Reactor and Nuclear Systems Division, Oak Ridge National Laboratory, Oak Ridge, TN























































