The present study discusses the source term derivation and dose result calculation for a hypothetical accident sequence in the Greek Research Reactor – 1 (GRR-1). A loss-of-coolant accident (LOCA) has been selected as a credible accident sequence. The source term derivation has been based on the GRR-1 confinement performance where the inventory has been computed assuming continuous reactor operation. A core damage fraction of 30% has been considered for the calculations while conservative core release fractions have been employed. The radionuclides released from the reactor core to the confinement atmosphere have been subjected to natural decay, deposition on and resuspension from various internal surfaces before being led to the release pathway. It has been assumed that an emergency shutdown is initiated immediately after the beginning of the accident sequence and the emergency ventilation system is also activated. Subsequently, the source term has been derived comprising of noble gases, iodine and aerosol. The JRODOS computational software for off-site nuclear emergency management has been utilized to estimate the dose results from the LOCA-initiated source term that is released in its entirety from the reactor stack at ambient temperature. The Local Scale Model Chain in conjunction with the DIPCOT atmospheric dispersion model that is embedded in JRODOS have been used with proper parameterization of the calculation settings. Five weather scenarios have been selected as representative of typical meteorological conditions at the reactor site. The scenarios have been assessed with the use of the Weather Research and Forecast model. Total effective, skin, thyroid, lung and inhalation doses downwind of the reactor building and up to a distance of 10 km have been calculated for each weather scenario and are presented. The total effective gamma dose rate at a fixed distance from the reactor building has been assessed. The radiological consequences of the dose results are discussed.
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2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4593-6
PROCEEDINGS PAPER
A Research Reactor Source Term and Dose Results in the Event of a LOCA
Charalampos Pappas,
Charalampos Pappas
National Center for Scientific Research “Demokritos”, Aghia Paraskevi, Attica, Greece
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Andreas Ikonomopoulos,
Andreas Ikonomopoulos
National Center for Scientific Research “Demokritos”, Aghia Paraskevi, Attica, Greece
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Athanasios Sfetsos,
Athanasios Sfetsos
National Center for Scientific Research “Demokritos”, Aghia Paraskevi, Attica, Greece
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Spyros Andronopoulos,
Spyros Andronopoulos
National Center for Scientific Research “Demokritos”, Aghia Paraskevi, Attica, Greece
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Melpomeni Varvayanni,
Melpomeni Varvayanni
National Center for Scientific Research “Demokritos”, Aghia Paraskevi, Attica, Greece
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Nicolas Catsaros
Nicolas Catsaros
National Center for Scientific Research “Demokritos”, Aghia Paraskevi, Attica, Greece
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Charalampos Pappas
National Center for Scientific Research “Demokritos”, Aghia Paraskevi, Attica, Greece
Andreas Ikonomopoulos
National Center for Scientific Research “Demokritos”, Aghia Paraskevi, Attica, Greece
Athanasios Sfetsos
National Center for Scientific Research “Demokritos”, Aghia Paraskevi, Attica, Greece
Spyros Andronopoulos
National Center for Scientific Research “Demokritos”, Aghia Paraskevi, Attica, Greece
Melpomeni Varvayanni
National Center for Scientific Research “Demokritos”, Aghia Paraskevi, Attica, Greece
Nicolas Catsaros
National Center for Scientific Research “Demokritos”, Aghia Paraskevi, Attica, Greece
Paper No:
ICONE22-31218, V003T06A056; 10 pages
Published Online:
November 17, 2014
Citation
Pappas, C, Ikonomopoulos, A, Sfetsos, A, Andronopoulos, S, Varvayanni, M, & Catsaros, N. "A Research Reactor Source Term and Dose Results in the Event of a LOCA." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security. Prague, Czech Republic. July 7–11, 2014. V003T06A056. ASME. https://doi.org/10.1115/ICONE22-31218
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