Workshops

Future Workshops

 

CASL Summer Institute

The Consortium for Advanced Simulation of Light Water Reactors (CASL) Institute will introduce participants to CASL and the Virtual Environment for Reactor Applications (VERA) framework and component codes.

Fifth COBRA-TF (CTF) User’s Group Meeting (CTF-5)

The fifth COBRA-TF (CTF) User’s Group (UG) Meeting (CTF-5) will be held on May 14-15, 2018 in in Lucca, Italy, and is a follow-up of the previous CTF UG meetings.

Twelfth Workshop of OECD/NEA Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs (LWR-UAM-12)

Twelfth Workshop of  OECD/NEA Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs (LWR-UAM-12) will take place on May 16-17, 2018 in Lucca, Italy in conjunction with BEPU-2018 conference on multi-physics and multi-scale simulations with uncertainty.

Third Workshop of OECD/NEA Deterministic Time-Dependent Neutron Transport Benchmark without Spatial Homogenization (C5G7-TD-3)

Third Workshop of OECD/NEA Deterministic Time-Dependent Neutron Transport Benchmark without Spatial Homogenization (C5G7-TD-3)  will take place on May 17-18, 2018 in Lucca, Italy in conjunction with BEPU-2018 conference on multi-physics and multi-scale simulations with uncertainty. 

 

Past Workshops
OECD/NEA LWR-UAM-11 BENCHMARK wORKSHOP

The OECD/NEA UAM-LWR Benchmark is an international high-visibility benchmark for uncertainty analysis in best-estimate coupled code calculations for design, operation, and safety analysis of LWRs. The benchmark activities are coordinated by the NCSU faculty: Dr. Maria Avramova and Dr. Kostadin Ivanov in cooperation with Dr. Eric Royer from CEA, France.

 

OECD/NEA C5G7-TD-2 bENCHMARK WORKSHOP

The OECD/NEA C5G7-TD Benchmark is an international Time-Dependent Neutron Transport Benchmark without Spatial Homogenization benchmark – C5G7-TD. The benchmarka ctvities are coordinated by the NCSU faculty: Dr. Jason Hou and Dr. Kostadin Ivanov in cooperation with Dr. Victor Boyarinov, from National Research Center  “Kurchatov Institute”, Russia.

 

CTF-4 USER GROUP mEETING

COBRA-TF is a thermal-hydraulic simulation code designed for Light Water Reactor (LWR) vessel and core analysis. It uses a two-fluid three-field modeling approach. CTF is the shortened name given to the version of COBRA-TF being developed and improved by the Reactor Dynamics and Fuel Modeling Group (RDFMG) at the North Carolina State University (NCSU).

 

MAVRIC/KENO, version SCALE 6.2.2 Workshop

This course provides instruction on the use of the KENO-VI Monte Carlo code for criticality safety calculations and the MAVRIC (Monaco with Automated Variance Reduction using Importance Calculations) shielding sequence with 3-D automated variance reduction for deep-penetration problems.

 

MCNP WORKSHOP

This is an introductory workshop to MCNP.

 

Multi-Physics Model Validation Workshop

The Nuclear Energy Knowledge and Validation Center (NEKVaC), INL in cooperation with the OECD/NEA Expert Group of Multi-physics Experiments, Benchmarks, and Validation (EGMPEBV), and with the support of Nuclear University Consortium (NUC), INL is sponsoring a Workshop on Multi-Physics Model Validation.

The workshop is hosted by the Nuclear Engineering Department (NED) at North Carolina State University (NCSU), and is supported by NEA/OECD international activities.