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Simulation of the gamma dose rate in a loss of pool water accident of the second Egyptian research reactor ET-RR-2

  • E. Amin , H. G. Saleh and N. Ashoub
Published/Copyright: March 17, 2022
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Abstract

The second Egyptian research reactor ET-RR-2, is a pool type reactor. A sudden loss of pool water would leave the core region uncovered. The reactor core is surrounded by chimney chambers with water isolated from the pool water. This accident would lead to significant external doses. A model is developed and used to calculate the dose rates for key access-areas and traffic plans from indirect line of sight of the core which have a maximum dose rate. The model developed uses the discrete ordinate method as implemented in the code DOT3.5.

Abstract

Der zweite ägyptische Forschungsreaktor ET-RR-2 ist ein Reaktor vom Pool-Typ, bei dem der plötzliche Verlust des Wassers im Pool den Reaktorkern unbedeckt lassen würde. Der Reaktorkern ist umgeben von Kammern, deren Wasser vom Pool-Wasser getrennt ist. Ein solcher Unfall würde zu einer erheblichen Strahlendosis führen. Ein Modell wurde entwickelt und angewendet zur Berechnung der Dosisleistungen für die Hauptzugangswege.

Das entwickelte Modell verwendet die Methode der diskreten Ordinaten, die auch im Programm-Code DOT3.5 verwendet wird.

References

1 Doster, J. M. and Hey, B. E.: Monte Carlo Simulation of Gamma Dose Rate in a Loss of Water Accident at North Carolina Sate University Research Reactor. Nucl. Sci. Eng. (1986)10.13182/NSE83-A17412Search in Google Scholar

2 Marzano, P.: Reactor Tank, Auxiliary Pool and Internals. General Assembly. 0767–0100- 2absm-001, (1994)Search in Google Scholar

3 Jatuff, F.; Lovotti, O.; Boado Magan, H.: Radiation Shielding of the Primary Coolant Circulation Rooms. 0767-0760-3TABL-253-10, 1994Search in Google Scholar

4 Rhoades, W. A.; Simpson, D. B.; Childs, R. L.; Engle, W. Jr.: DOT3.5 Two Dimensional Discrete Ordinates Radiation Transport Code, ORNL-RISC-CCC 276 (1977)Search in Google Scholar

5 American National Standard, Neutron and Gamma Ray Flux to Dose Rate Factors, ANSI/ANS-6.1.1-1977 (1977)Search in Google Scholar

6 AEA: Safety Evaluation Report for the Second Egyptian Research Reactor, ET-RR-2 SER/01/1997 (1997)Search in Google Scholar

7 Soltesz, R. G; Disney, R. K.: ANISN, Multigroup One- Dimensional, Discrete Ordinates Transport Code with Anisotropic Scattering, ORNL-RISC-CCC 254 (1979)Search in Google Scholar

8 Garber, D.: ENDF/B Summary Documentation BNL-NCS-17541 (ENDF-201), 2nd ed. (ENSD/B-IV), (1975)Search in Google Scholar

9 Esposto, F.; Lovotti O.; and Boado, J.: Shielding of the Control Rod Drives Room Using Heavy Reinforced Concrete Without Coarse aggregate, 0767-0810-3TABL-265-10, (1994)Search in Google Scholar

Received: 2001-12-10
Published Online: 2022-03-17

© 2002 Carl Hanser Verlag, München

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