Impact of switching to the ICRP-74 neutron flux-to-dose equivalent rate conversion factors at the Sandia National Laboratory Building 818 Neutron Source Range.

Estimation of low-level neutron dose-equivalent rate by using extrapolation method for a curie level Am–Be neutron source

Applied Radiation and Isotopes ◽

10.1016/j.apradiso.2014.10.010 ◽

2015 ◽

Vol 95 ◽

pp. 122-128 ◽

Cited By ~ 1

Author(s):

Gang Li ◽

Jiayun Xu ◽

Jie Zhang

Keyword(s):

Neutron Source ◽

Neutron Dose ◽

Extrapolation Method ◽

Dose Equivalent ◽

Low Level ◽

Equivalent Rate ◽

Neutron Dose Equivalent

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The neutron production rate measurement of an indigenously developed compact D-D neutron generator

Nuclear Technology and Radiation Protection ◽

10.2298/ntrp1304422d ◽

2013 ◽

Vol 28 (4) ◽

pp. 422-426

Author(s):

Basanta Das ◽

Anurag Shyam ◽

Rashmita Das ◽

Durga Rao

Keyword(s):

Neutron Flux ◽

Neutron Generator ◽

Flux Measurement ◽

Ion Source ◽

Equivalent Rate ◽

Titanium Target ◽

Compact Neutron Generator ◽

Rate Conversion ◽

Deuterium Gas ◽

Technology Industries

One electrostatic accelerator based compact neutron generator was developed. The deuterium ions generated by the ion source were accelerated by one accelerating gap after the extraction from the ion source and bombarded to a target. Two different types of targets, the drive - in titanium target and the deuteriated titanium target were used. The neutron generator was operated at the ion source discharge potential at +Ve 1 kV that generates the deuterium ion current of 200 mA at the target while accelerated through a negative potential of 80 kV in the vacuum at 1.3?10-2 Pa filled with deuterium gas. A comparative study for the neutron yield with both the targets was carried out. The neutron flux measurement was done by the bubble detectors purchased from Bubble Technology Industries. The number of bubbles formed in the detector is the direct measurement of the total energy deposited in the detector. By counting the number of bubbles the total dose was estimated. With the help of the ICRP-74 neutron flux to dose equivalent rate conversion factors and the solid angle covered by the detector, the total neutron flux was calculated. In this presentation the operation of the generator, neutron detection by bubble detector and estimation of neutron flux has been discussed.

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