International Workshop on Numerical Modelling of NDA Instrumentation and Methods for Nuclear Safeguards

NM NDA IMNS18

The ESARDA Non-Destructive Assay (NDA) Working Group is organising an international workshop on the topics of computer simulation applied to the modelling of NDA instrumentation and methods for nuclear safeguards applications. The two day event aims to cover a broad range of topics and present a unique opportunity for the safeguards community interested in recent advances and in lessons learned from practical cases.

Please note, the workshop will be co-hosted during the ESARDA 40th Annual Meeting being held in Luxembourg. In order to accommodate the workshop, the dates have changed to 16th-17th May, 2018. For more information on the event please visit the ESARDA 40th Annual Meeting page.

You are invited to present your work in the field of numerical modelling, especially covering activities related to:

  • Neutron and Gamma Detection Systems
  • Spent fuel measurements
  • Benchmarking
  • New Radiation Sensors
  • Calibration/Sensitivity Studies
  • Variance Reduction Application in NDA Instrument Response Simulation
  • Non Radiation Transport Codes – Dead time correction, Pulse train analysis,…
  • New Fission Models

Call for Abstract
Please submit a short (300 words maximum) abstract by: Extended to 31/01/2018.
Proceedings of the Workshop will be published and a short written paper will need to be submitted before 1st May 2018.

Organisers

  • Workshop Chair: Ludovic Bourva
  • Organisation: Peter Jansson

Workshop Presentations

Session 1 - Chair: Alessandro Borella (SCK●CEN)

 

Topic: Spent Fuel Applications

Title File
Spent Fuel Assembly Characterization by a Passive Neutron Albedo Reactivity Instrument as a part of an Integrated NDA System for Encapsulation Safeguards
(V. Litichevskyi et al)
PDF
Modelling Passive Fast-Neutron Emission Tomography of Spent Nuclear Fuel
(P. Hausladen et al)
PDF
Performance Evaluation Framework for the Passive Gamma Emission Tomography (PGET) System
(T. White et a)
PDF 
Geometry-based Variance Reduction in simulations of Passive Gamma Spectroscopy from Spent Nuclear Fuel
(Z. Elter et al)
PDF

 

Topic: New Detector Modelling

Title File
Solid state Silicon + 6 LiF thermal neutron detectors: Geant4 simulations versus real data
(P. Finocchiaro et al)
PDF
Integrated System Based On Muon Tomography for Nuclear Security and Safeguards
(O. Kamaev et al)
PDF 
A Semi-empirical Approach to Validating Results from a Fast-neutron Coincidence Collar
(J. Beaumont et al)
PDF 

 

Session 2 - Chair: Louise Worrall (ORNL)

 

Topic: NDA Applications

Title File
Use of neutron coincidence counters for the estimation of fissile content in irradiated material
(R. Rossa et al)
PDF
Advancements in high-fidelity simulations of detector response for nuclear safeguards applications
(V. Henzl and A. Favalli)
PDF 
MCNP simulation study of fast neutron and gamma coincidence detection system for nuclear security and safeguards applications
(D. Trombetta et al)
PDF 
Simulation of a neutron multiplicity counter and comparison to validation experiments
(O. Schumann et al)
PDF 
Monte Carlo simulations for determination of the 235 U enrichment with the infinite thickness methodology
(A. Borella and R. Rossa)
PDF 
Comparison of the Response of Handheld Neutron Detectors: Measurements and Calculations
(M.Baron et al)
PDF
Using MCNP to Reduce the Background Sensitivity of a Non-Destructive Assay Passive Neutron Co-incidence Counting Chamber
(V. Baldioli et al)
PDF

 

Session 3 - Chair: Peter Jansson (U. of Uppsala)

 

Topic: Spent Fuel Applications

Title File
Advanced Experimental Fuel Counter (AEFC) Model Results Compared to Measurements of Irradiated IRT Assemblies
(A. Trahan et al)
PDF
MCNP simulations of prototype DDSI detector
(L. Caldeira Balkeståhl et al)
PDF
Modelling of a neutron detector for measurements of spent fuel pellets
(P. Schillebeeckx et al)
PDF
Nuclear data sensitivity study for NDA on spent nuclear fuel
(G. Žerovnik et al) 
PDF

 

Topic: Nuclear Data and Post Processing

Title File
Preliminary Insights from the Assessment of Nuclear Data Needs for Nonproliferation
(T. Ault et al)
PDF
 Numerical Method for High Count-Rate Dead-Time Correction in Neutron Multiplicity Counting using Multi-Channel List-Mode Recorders
(L. Holzleitner et al)
PDF
 Nondestructive assay in the Role of Consistency Checking
(T. Burr et al)
PDF