Radiation Protection and Environment

ARTICLE
Year
: 2011  |  Volume : 34  |  Issue : 3  |  Page : 153--156

Neutron and gamma dose measurement in the working area of a research reactor using passive dosimeters


Deepa Sathian1, AK Bakshi1, Sajin Prasad2, N Kalyanasundaram2, MP Chougaonkar1 
1 Radiological Physics & Advisory Division, Bhabha Atomic Research Centre, Mumbai, India
2 Radiation Safety and System Division, Bhabha Atomic Research Centre, Mumbai, India

Correspondence Address:
A K Bakshi
Radiological Physics & Advisory Division, Bhabha Atomic Research Centre, Mumbai
India

Radiation dose measurement at selected locations around the experimental facilities of a research reactor was carried out. Passive dosimeters based on CR-39 and CaSO 4 :Dy Teflon disc and 6 LiF:Mg,Ti and 7 LiF:Mg,Ti based neutron and gamma dosimeters were used in the study for the measurement of ambient dose equivalent (H*(10)). Measured neutron and gamma dose equivalent rates were found to be within the stipulated limit as per the guidelines of Atomic Energy Regulatory Board (the regulatory authority of India) for the radiation workers.


How to cite this article:
Sathian D, Bakshi A K, Prasad S, Kalyanasundaram N, Chougaonkar M P. Neutron and gamma dose measurement in the working area of a research reactor using passive dosimeters.Radiat Prot Environ 2011;34:153-156


How to cite this URL:
Sathian D, Bakshi A K, Prasad S, Kalyanasundaram N, Chougaonkar M P. Neutron and gamma dose measurement in the working area of a research reactor using passive dosimeters. Radiat Prot Environ [serial online] 2011 [cited 2021 Jan 17 ];34:153-156
Available from: https://www.rpe.org.in/article.asp?issn=0972-0464;year=2011;volume=34;issue=3;spage=153;epage=156;aulast=Sathian;type=0