Home About us Editorial board Search Ahead of print Current issue Archives Submit article Instructions Subscribe Contacts Login 
Home Print this page Email this page Small font size Default font size Increase font size Users Online: 1020
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

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
Login to access the Email id

Source of Support: None, Conflict of Interest: None

DOI: 10.4103/0972-0464.101681

Rights and Permissions

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.

Print this article     Email this article
Next article
Previous article
Table of Contents
Similar in PUBMED
   Search Pubmed for
   Search in Google Scholar for
 Related articles
Citation Manager
Access Statistics
Reader Comments
Email Alert *
Add to My List *
 * Requires registration (Free)

 Article Access Statistics
    PDF Downloaded395    
    Comments [Add]    

Recommend this journal