Calculation of liquid waste discharge limits for routine discharge of Tehran research reactor
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M. E. Adelikhah
Abstract
One of the most important technical documents for obtaining of a reactor license (site selection, design, construction and operation license) from IINRA is public dose assessment and calculation of discharge limits into the environment. Presence of population centers and aquifers adjacent of nuclear installations is a crucial rule in public dose assessment and determination of liquid release limits into the environment. In this paper, liquid waste of TRR regards as liquid released in sewage system. The migration of radionuclides released to well through the ingestion of radionuclides via drinking water and human food-chain, inhalation of radionuclides and external irradiation from radionuclides in soil and water was modeled using the AMBER software. Then, amount of liquid released to environment with different amount of distribution coefficient, as an important effective parameter in simulation, is determined. The calculation of discharge limits shows that the liquid radioactive waste is lower than the values given into the Environmental Assessment for Tehran Research Reactor report. So the received dose doesn't exceed the dose limit of 10 μSvyr−1 for members of the public which is approved by INRA.
Kurzfassung
Die Bestimmung der von der Anlage verursachten Dosen für die Bevölkerung und die Berechnung der von der Anlage an die Umwelt abgegebenen Stoffe waren wichtige Bestandteile bei der Betriebsgenehmigung (Standortwahl, Planung, Bau- und Betriebsgenehmigung) des Forschungsreaktors Tehran (TRR) durch IINRA. Dabei müssen sowohl die bewohnten Gebiete als auch die Grundwassereinzugsgebiete bei der Berechnung und Festlegung der Grenzwerte berücksichtigt werden. In diesem Beitrag wird der Unterpunkt flüssiger Abfall des TRR, der in das Abwassersystem freigesetzt wird, betrachtet. Dazu wird eine neue Berechnung mit dem Programm AMBER durchgeführt. Dabei wird die Migration von Radionukliden, die durch die Aufnahme von Radionukliden über Trinkwasser und die menschliche Nahrungskette, die Inhalation von Radionukliden und die externe Bestrahlung von Radionukliden in Boden und Wasser in den Brunnen freigesetzt werden, berücksichtigt. Anschließend wird die Menge der in die Umgebung freigesetzten Flüssigkeit mit unterschiedlichem Verteilungskoeffizienten als wichtigstem Parameter der Simulation bestimmt. Die Berechnung der Ableitungsgrenzwerte zeigt, dass die Dosis der flüssigen radioaktiven Abfälle unterhalb des genehmigten Grenzwertes von 10 μSvyr-1 für die Öffentlichkeit liegt.
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© 2018, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- Porosity evolution study in irradiated UO2 fuel based on fuel matrix swelling
- Data collection assessment for the human performance analysis in nuclear installations
- Abnormal control rod withdrawal analysis for innovative research reactor using PARET-ANL codes
- Improving CANDU performance by using uranium – thorium mixed oxide fuel
- Computation of gamma radioactivity of natural rocks in the vicinity of Antalya province and its effect on health
- Calculation of liquid waste discharge limits for routine discharge of Tehran research reactor
- Thermal hydraulic assessment of a new design of PWR fuel assembly
- Simulation of error in suppression of Xenon oscillations in a WWER-1000 nuclear reactor
- A novel dual-molality densitometer for gauging in annular two phase flows using radial basis function
- Design and construction of toroidal field coil for Taban device
Articles in the same Issue
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- Porosity evolution study in irradiated UO2 fuel based on fuel matrix swelling
- Data collection assessment for the human performance analysis in nuclear installations
- Abnormal control rod withdrawal analysis for innovative research reactor using PARET-ANL codes
- Improving CANDU performance by using uranium – thorium mixed oxide fuel
- Computation of gamma radioactivity of natural rocks in the vicinity of Antalya province and its effect on health
- Calculation of liquid waste discharge limits for routine discharge of Tehran research reactor
- Thermal hydraulic assessment of a new design of PWR fuel assembly
- Simulation of error in suppression of Xenon oscillations in a WWER-1000 nuclear reactor
- A novel dual-molality densitometer for gauging in annular two phase flows using radial basis function
- Design and construction of toroidal field coil for Taban device
