Limit occupancy: no more than 25 attendees per workshop and they will be accepted in a first come first serve basis, date for first registration will be announced.
Workshop Fee: a recovery cost will be charged and it will be announced.
Schedule: Sunday April 22, 2018 and time will be announced.
NJOY Processing System Workshop
Topics to be covered
1. Introduction to the ENDF file format.
2. Introduction to modules needed to create a continuous-energy neutron ACE file.
3. How to use the processed data in MCNP.
4. How to plot nuclear data with NJOY.
After enrollment, a week prior to PHYSOR, it will be sent to the participants an email informing them of things they should download before the workshop.
There will be access to wireless internet so that the participants can download various NJOY input decks and such.
Participants should bring their own computer and should have NJOY installed prior to the beginning of the class.
Real-Time Particle Transport Simulations - MRT Methodology & RAPID code system Workshop
The goal of this workshop is to introduce the audience to the novel Multi-stage, Response-function Transport (MRT) methodology1, a Physics-based computational technique, for real-time simulation of nuclear systems. Further, it elaborates on a number of MRT-based computational tools developed for solving real-world problems in real time. Particularly, the workshop will emphasize on the recently developed RAPID code system2, 3 by giving real-time demonstration of the use of the code for solving real-world problems, e.g., a cask containing 32 spent fuel assemblies, on a laptop in real time!
The workshop will include two parts:
Part I: Discussion of the MRT methodology and its application for a few real-world problems:
- AIMS (Active Interrogation for Monitoring of SNM).
- INSPCT-S tool (INSPCT-S, Inspection of Nuclear Spent fuel-Pool Calculation Tool ver. Spreadsheet).
- TITAN-IR (TITAN code system for Image Reconstruction).
- RAPID (Real-time Analysis Particle-transport In-situ Detection).
Part II: Demonstration of the RAPID code system for simulation of spent fuel casks and pools
In a MRT methodology, the problem of interest is partitioned into stages based on its physics, and each stage is represented by a response function or set of coefficients. These stages are combined into a linear system of equations which are solved iteratively using the pre-calculated functions and/or coefficients.
1. Haghighat, K. Royston and W. Walters, “MRT Methodologies for real-time simulation of nonproliferation and safeguards problems, Annals of Nuclear Energy, Volume 87, Part 1, pp 61-67, January 2016.
2. W. Walters, N. Roskoff, and A. Haghighat, “A Fission Matrix Approach to Calculate Pin-wise 3D Fission Density Distribution,” Proc. M&C 2015, Nashville, Tennessee, April 19-23, 2015.
3. V. Mascolino, A. Haghighat, and N. Roskoff, “Evaluation of RAPID for a UNF Cask Benchmark Problem,” Proc. ICRS-13 & RPSD-2016, Paris, France, October 3-6, 2016.
There will be access to wireless internet so that the participants can have remote access to the software.
A Personal Computer, iPad, Tablet, etc.