Since 18 of December 2019 conferences.iaea.org uses Nucleus credentials. Visit our help pages for information on how to Register and Sign-in using Nucleus.

Preoperational and operational radiomonitoring and radiation protection program of Iran near-surface disposal facility

Not scheduled
20m
M-Building (IAEA Headquarters, Vienna)

M-Building

IAEA Headquarters, Vienna

Vienna International Center - Wagramer Str 5 - PO Box 100, 1400 Vienna, Austria
POSTER Track 5 - Practical experiences in integrating safety and sustainable development

Speakers

Mr Mehdi Boroumandi (Iran Radioactive Waste Management Co./ AEOI)Mr Saeed Zare Ganjaroodi (Iran radioactive waste management company/ AEOI;Faculty of energy and physics, Amirkabir university)

Description

The main goal of this paper is to investigate the preoperational and operational radiomonitoring program for near-surface disposal in the Anarak radioactive waste near-surface trench-type repository in Iran using both experimental and simulation methods. Barrels containing solid and solidified radioactive waste and concrete overpacks are planning to dispose into the near-surface disposal trenches. In such a manner, a comprehensive radiomonitoring plan is designed for the Anarak waste repository including, main pathways, sampling methods, sampling frequency, radionuclides concertation analysis, and radiation protection design for both preoperational and operational periods. Finally, all measured values were evaluated with national and international standards to demonstrate that the radioactive release into the environment is less than the permissible limit to ensure the safety of people and the environment. Results of analysis presented that, concentrations of radionuclides in soil, water, and air particulates samples are at environmental background level which determined in preoperational period and variations in operational periods compared to pre-operational phase shows there in no meaningful changes. On the other hand, Monte Carlo modeling of radiation protection of the Anarak site have done for operational purpose and the maximum dose released from solid and solidified radioactive waste overpacks at 1 (m) distance are calculated.

Primary authors

Mr Mehdi Boroumandi (Iran Radioactive Waste Management Co./ AEOI) Mr Saeed Zare Ganjaroodi (Iran radioactive waste management company/ AEOI;Faculty of energy and physics, Amirkabir university) Ali Malekifarsani Saber Hassanlou (Iran Radioactive Waste Management Co. (IRWA))

Presentation materials