Calculation of the accidental gamma dose rate at the top of the low power research reactor Online publication date: Wed, 04-May-2016
by S. Dawahra; G. Saba
International Journal of Nuclear Energy Science and Technology (IJNEST), Vol. 10, No. 1, 2016
Abstract: Owing to the high risk through conducting the experiment of losing the core water shield, the analytical and statistical (MCNP) methods were used to estimate the gamma dose rate at the reactor top when the core water shield level decreases to the value less than the Miniature Neutron Source Reactor (MNSR) safety limit. For normal operation condition, the results showed that the core water shield attenuated the gamma dose rate by 3 × 106 times. The gamma dose rate values at the reactor top due to the core and the water impurities were 46.8, 89.9 and 52 μSv.h−1 for the statistical, analytical calculations and experimental reference value respectively. For the accidental condition (the core water shield level is 12 cm), the results showed that the maximum gamma dose rate value at the reactor top was 1.4 × 10−8 μSv.h−1. Therefore, no one should stay at the reactor top if an accident occurs. These results of dose rate can be used as reference values in order to set the radiation protection requirements in the MNSR reactor.
Existing subscribers:
Go to Inderscience Online Journals to access the Full Text of this article.
If you are not a subscriber and you just want to read the full contents of this article, buy online access here.Complimentary Subscribers, Editors or Members of the Editorial Board of the International Journal of Nuclear Energy Science and Technology (IJNEST):
Login with your Inderscience username and password:
Want to subscribe?
A subscription gives you complete access to all articles in the current issue, as well as to all articles in the previous three years (where applicable). See our Orders page to subscribe.
If you still need assistance, please email subs@inderscience.com
Our Blog 
Follow us on Twitter 
Visit us on Facebook