Meetings

Data Analysis in Nuclear Criticality Safety-I

The Zeus Copper/Uranium Critical Experiment at NCERC, Rene Sanchez, David Hayes, Joetta Goda, John Bounds, Kevin Jackman(LANL)

Reverse Engineering the MOX International Standard, ISO/CD 11311, “Critical Values for Homogenous Plutonium-Uranium Oxide Fuel Mixtures (MOX) Outside of Reactors,” Jason E. Huffer(URS Corporation)

Criticality Safety Validation of SCALE 6.1 with ENDF/B-VII.0 Libraries, W. J. Marshall, B. T. Rearden (ORNL)

Examination of Validation Outlier Cases Using the Sensitivity and Uncertainty Analysis Tools of SCALE 6.1, B. T. Rearden, W. J. Marshall (ORNL)

Advancing Criticality Safety Capabilities in a Growing Nuclear World

Methods for Detector Placement and Analysis of Criticality Accident Alarm Systems, Douglas E. Peplow (ORNL), Larry L. Wetzel (Babcock & Wilcox, NOG-L)

Continuous-S (a,b) Capability in MCNP, Jeremy Lloyd Conlin, D. Kent Parsons, Forrest B. Brown, Robert E. MacFarlane, Robert C. Little, Morgan C. White (LANL)

The Double Contingency Principle and Subcriticality Revisited, Christopher S. Tripp, Dennis C. Morey (NRC)

Continuous-Estimator Representation for Monte Carlo Criticality Diagnostics, Brian C. Kiedrowski, Forrest B. Brown (LANL)

Evaluation of Computing c-Eigenvalues with Monte Carlo, Brian C. Kiedrowski (LANL)

Data Analysis in Nuclear Criticality Safety-II
Tues. p.m.

Cross Section Data Benchmarking Using Automated Criticality Benchmarks in MCNP6 and Partisn, Eric Relson (LANL/Univ of Wisconsin- Madison), Jeremy Lloyd Conlin, D. Kent Parsons (LANL)

Benchmark Evaluation of GROTESQUE, a Complex Arrangement of HEU Metal Pieces, John D. Bess (INL), Mackenzie L. Gorham (Idaho State Univ)

Radiation Damage to Neutron Absorber Materials for Cask Spent Fuel Storage, Benjamin Baranko (Nuclear Safety Associates)

Comparison Between GEMER and MCNP5 in Stochastic Geometry Modeling of Heterogeneous Fissile Media for Criticality Computations, Qi Ao (GE Hitachi Nuclear)

Comparison of HEU Measurements Using Measured and Simulated Data, J. Hutchinson, A. Sood, W. Myers, M. Smith-Nelson, D. Dinwiddie (LANL)

An Evaluation of Monte Carlo Simulations of Neutron Multiplicity Measurements of Plutonium Metal, John Mattingly (NCSU), Eric Miller (Univ of Michigan), C. J. Solomon (LANL), Ben Dennis, Amy Meldrum, Shaun Clarke, Sara Pozzi (Univ of Michigan)

Benchmarking Experiments for Criticality Safety and Reactor Physics Applications-I

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) were established to identify and evaluate a comprehensive set of criticality safety and reactor physics related experimental data and preserve the data in a form that will be easily accessible to users. The projects provide a basis for recording, developing, and validating computational and analytical methods. Topics consist of the importance of quality experimental measurements, benchmark model development, uncertainty quantification, and utilization of these benchmarks in real-world applications.
PANELISTS:

John Bess (INL)

David Hayes(LANL)

Dick McKnight (ANL) (no slides were used)

Jim Gulliford (OECD/NEA)

Fitz Trumble (WSMS)

Skip Kahler (LANL)

Benchmarking Experiments for Criticality Safety and Reactor Physics Applications-II

The International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) were established to identify and evaluate a comprehensive set of criticality safety and reactor physics related experimental data and preserve the data in a form that will be easily accessible to users. The projects provide a basis for recording, developing, and validating computational and analytical methods. This tutorial will outline and discuss the benchmark process for the ICSBEP and IRPhEP. Attendees will also be provided with a brief demonstration of DICE (Database for the International Handbook of Evaluated Criticality Safety Benchmark Experiments), and receive a preliminary introduction to IDAT (International Reactor Physics Experiment Evaluation Database and Analysis Tool) prior to its release. Participants are encouraged to request their free copies of the handbooks at http://icsbep.inl.gov/ and http://irphep.inl.gov/ . Questions can be addressed by e-mail: john.bess@inl.gov.>

Benchmark Tutorial — I –

Introduction>
Benchmark Tutorial — II –Availability

Benchmark Tutorial — IIb –IDAT Demo

Benchmark Tutorial — III –Report

Benchmark Tutorial — IV –Participation