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Title: Simulation of cargo container interrogation by D-D neutrons.

Abstract

No abstract prepared.

Authors:
 [1];  [2]
  1. (Lawrence Berkeley National Laboratory, CA)
  2. (Sandia National Laboratories, Livermore, CA)
Publication Date:
Research Org.:
Sandia National Laboratories
Sponsoring Org.:
USDOE
OSTI Identifier:
903146
Report Number(s):
SAND2007-0512C
TRN: US0703134
DOE Contract Number:
AC04-94AL85000
Resource Type:
Conference
Resource Relation:
Conference: Proposed for presentation at the Mathematics & Computing + Supercomputing in Nuclear Applications held April 15-19, 2007 in Monterey, CA.
Country of Publication:
United States
Language:
English
Subject:
72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS; CARGO; CONTAINERS; NEUTRONS; SIMULATION; COMPUTERS; SUPERCOMPUTERS

Citation Formats

Lou, Tak Pui, and Antolak, Arlyn J. Simulation of cargo container interrogation by D-D neutrons.. United States: N. p., 2007. Web.
Lou, Tak Pui, & Antolak, Arlyn J. Simulation of cargo container interrogation by D-D neutrons.. United States.
Lou, Tak Pui, and Antolak, Arlyn J. Mon . "Simulation of cargo container interrogation by D-D neutrons.". United States. doi:.
@article{osti_903146,
title = {Simulation of cargo container interrogation by D-D neutrons.},
author = {Lou, Tak Pui and Antolak, Arlyn J.},
abstractNote = {No abstract prepared.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 2007},
month = {Mon Jan 01 00:00:00 EST 2007}
}

Conference:
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  • High fidelity, three-dimensional computer models based on a CAD drawing of an intermodal cargo container, representative payload objects, and detector array panels were developed to simulate the underlying physical events taking place during active interrogation. These computer models are used to assess the performance of interrogation systems with different sources and detection schemes. In this presentation, we will show that the use oversimplified models, such as analyzing homogenized payloads only, can lead to errors in determining viable approaches for interrogation.
  • Several different fast-neutron based techniques are being studied for the detection of contraband substances in luggage and cargo containers. The present work discusses the accelerator requirements for fast-neutron transmission spectroscopy (FNTS), pulsed fast-neutron analysis (PFNA), and 14-MeV neutron interrogation. These requirements are based on the results of Monte-Carlo simulations of neutron or gamma detection rates. Accelerator requirements are driven by count-rate considerations, spatial resolution and acceptable uncertainties in elemental compositions. The authors have limited their analyses to luggage inspection with FNTS and to cargo inspection with PFNA or 14-MeV neutron interrogation.
  • The authors present calculations of photon spectra observed following irradiation of bare HEU, HEU embedded in steel and wood cargos, and steel and wood alone. These spectra might be useful starting points for statistical detection efforts aimed at determining whether fissile material is present in a cargo. Detailed comparisons between calculations and experiments are presented and overall quite good (small {chi}{sup 2}) agreement is found. they do not present a complete solution to the problem of determining whether a given spectrum contains contributions from post-fission photons. However, it is shown that a brute-force fitting of observed spectra in terms ofmore » a few calculated ''basis'' spectra gives meaningful predictions about the presence of {sup 235}U in cargo. Though this may not be the most powerful method, it does give well defined confidence limits and seems to have strong predictive power.« less
  • We describe the results of a Monte Carlo simulation 10 investigate the feasibility of using a pulsed deuterium-tritium (D-T) neutron technique for active interrogation of special nuclear material in cargo containers. Time distributions of fission neutrons from highly enriched uranium induced by a pulsed D-T neutron source were calculated for cargo containers with different hydrogen contents. A simple detector system with polyethylene and cadmium was modeled to calculate the two-group neutron flux at the detector.