NDLI: Neutron Transport Characteristics of a Nuclear Reactor Based Dynamic Neutron Imaging System

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Anas, M. Khaial Glenn, D. Harvel Chang, Jen-Shih
Copyright Year	2006
Abstract	An advanced dynamic neutron imaging system has been constructed in the McMaster Nuclear Reactor (MNR) for nondestructive testing and multi-phase flow studies in energy and environmental applications. A high quality neutron beam is required with a thermal neutron flux greater than 5.0×106 n/cm2-s and a collimation ratio of 120 at image plane to promote high-speed neutron imaging up to 2000 frames per second. Neutron source strength and neutron transport have been experimentally and numerically investigated. Neutron source strength at the beam tube entrance was evaluated experimentally by measuring the thermal and fast neutron fluxes, and simple analytical neutron transport calculations were performed based upon these measured neutron fluxes to predict facility components in accordance with high-speed dynamic neutron imaging and operation safety requirements. Monte-Carlo simulations (using MCNP-4B code) with multiple neutron energy groups have also been used to validate neutron beam parameters and to ensure shielding capabilities of facility shutter and cave walls. Neutron flux distributions at the image plane and the neutron beam characteristics were experimentally measured by irradiating a two-dimensional array of Copper foils and using a real-time neutron radiography system. The neutron image characteristics — such as neutron flux, image size, beam quality — measured experimentally and predicted numerically for beam tube, beam shutter and radiography cave are compared and discussed in detail in this paper. The experimental results show that thermal neutron flux at image plane is nearly uniform over an imaging area of 20.0-cm diameter and its magnitude ranges from 8.0×106 – 1.0×107 n/cm2-sec while the neutron-to-gamma ratio is 6.0×105 n/cm2-μSv.
Sponsorship	Nuclear Engineering Division
Starting Page	409
Ending Page	417
Page Count	9
File Format	PDF
ISBN	0791842444
DOI	10.1115/ICONE14-89504
e-ISBN	0791837831
Volume Number	Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy
Conference Proceedings	14th International Conference on Nuclear Engineering
Language	English
Publisher Date	2006-07-17
Publisher Place	Miami, Florida, USA
Access Restriction	Subscribed
Subject Keyword	Neutron radiography Neutron flux Copper foil Multiphase flow Neutron sources Neutrons Nondestructive evaluation Simulation Imaging Neutron beams Caves Flux (metallurgy) Nuclear reactors Engineering simulation Safety
Content Type	Text
Resource Type	Article

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