CANUTRON — A clean accelerator neutron generator

Chidley, B. G.; McMichael, G.E.; Schriber, S. O.

doi:10.1016/0168-583x(85)90131-4

Cited by 7 publications

(2 citation statements)

References 2 publications

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“…Reactor-based neutron radiography allows excellent resolution of spatial details and sufficient beam intensity to radiograph through thick aerospace structures, even with some amount of neutron-absorbing materials in the beam path. The recent development of compact, high-current accelerators (Ref 11,12, and f3), however, now offers the exciting possibility of developing powerful neutron radíography inspection systems with beam intensities approaching those of nuclear reactors, but at much lower cost and with greatly reduced radiological hazard and improved radiographic flexibility. While such a system would be considerably more expensive than inspection systems using more traditional" techniques such as X-rays and ultrasonics, for example, this must be balanced against the unique inspection information obtained and the cost of the premature replacement of flight-worthy aircraft .…”

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confidence: 99%

Neutron radiography of aerospace structure hidden corrosion

Swanson¹,

Kamykowski²,

Horn³

et al. 1995

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The detection of corrosion in operational aircraft is vital for an effective repair and maintenance program intended to extend the service lifetimes of these aircraft. Neutron radiography is an established non-destructive inspection technique that can detect early-stage corrosion, even within retatively thick aluminum structures. This report presents the results of a study to measure experimentally the detection sensitivity of ncutroR raciiography to aircrait corrosion, using both laboratory-prepared and environmentally produced aircratt corrosion specirnens. Thermal neutrons were obtained from the medical research reactor at the DOE's Brookhaven National Laboratory (BNL) as part of a Cooperative Research and Development Agreement (CRADA) between Northrop Grumman Corporation and BNL. Initial work at the reactor consisted of enhancing the beam collimation for high-resolution radiography. The neutron beam conditions were then measured using activation foils and several commercial beam-quality indicators. Radiography of the corrosion specimens was carried out with a vacuum cassette employing a gadoliniurn converter screen and finegrain X-ray film. Measurement of the optical film density of the corrosion images allowed an evaluation of the etfective thermal neutron anenuation coetficient for corrosion products. This evaluation was facilitated by the use of water specirnens to calibrate the measurement procedure, since water has a known thermal neutron attenuation coefficient. An assessment of the thickness threshold for visually distinguishing corrosion by-products in neutron radiographs indicated a threshòU ot about 2 mils (0.002 in.) for the laboratory-prepared corrosion and less than that for the aircraft corrosion samples examined. The experimental results obtained with the BNL reactor thermal-neutron beam were used to help predict the potential capability of an accelerator-based neutron radiography system that could be deployed in a hangar type of environment to inspect either intact aircraft or subassemblies from such aircraft.

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confidence: 99%

Neutron radiography of aerospace structure hidden corrosion

Swanson¹,

Kamykowski²,

Horn³

et al. 1995

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“…Throughout its 65-year history, Atomic Energy of Canada Limited, now Canadian Nuclear Laboratories (CNL), has been a leader in developing shielding methodologies and performing calculations for reactor and nuclear facilities designs [2][3][4], accelerators [5,6], and other medical applications such as the 60 Co cancer therapy machine [7]. Recently, CNL has been growing its capability by developing advanced shielding analysis methods for emergency preparedness [8,9], waste management [10], and medical applications such as cyclotron shielding design.…”

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confidence: 99%

Emerging Areas of Shielding Research—a Bird’s Eye View

Dranga

Adams

2019

CNL Nuclear Review

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BackgroundRadiation shielding technology has its origins in the 1890s with the discovery of X-rays and gamma rays, their early applications, and the associated hazards that came with them [1]. The main goal of this technology is to protect workers and the public from the detrimental effects of high levels of radiation by designing physical barriers that reduce the radiation dose.Throughout its 65-year history, Atomic Energy of Canada Limited, now Canadian Nuclear Laboratories (CNL), has been a leader in developing shielding methodologies and performing calculations for reactor and nuclear facilities designs [2][3][4], accelerators [5,6], and other medical applications such as the 60 Co cancer therapy machine [7]. Recently, CNL has been growing its capability by developing advanced shielding analysis methods for emergency preparedness [8,9], waste management [10], and medical applications such as cyclotron shielding design. Similarly, other research centres in Canada (e.g., Canadian Space Agency, universities, Defence Research and Development Canada, etc.) have been carrying out research in shielding analysis and new materials development. Other applications in addition to those described above (e.g., manned deep space exploration and development of lightweight and efficient materials for radiation protection) are gaining importance due to technological advances as well as increased need by private industries and the research community.This paper provides a high-level summary of emerging research areas for shielding analysis and their current status and evaluates these areas in terms of rewards to the scientific community and industry, such as potential for marketable materials and devices, novel methodologies that would increase efficiency and cost savings, cross-disciplinary applications, and development of expertise and highly qualified personnel. Identification of Research AreasFor this assessment, shielding analysis was identified as a required component of research and development (R&D) activities in the following 6 areas:1. remote reactor monitoring, 2. source reconstruction and inverse shielding methods, For personal use only.

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Nuclear Data for Geology and Mining

Csikai

1992

Nuclear Data for Science and Technology

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CANUTRON — A clean accelerator neutron generator

Cited by 7 publications

References 2 publications

Neutron radiography of aerospace structure hidden corrosion

Neutron radiography of aerospace structure hidden corrosion

Emerging Areas of Shielding Research—a Bird’s Eye View

Nuclear Data for Geology and Mining

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