DIONISIO is a computer code designed to simulate the behavior of one nuclear fuel rod during its permanence within the reactor. Starting from the power history and the external conditions to which the rod is subjected, the code predicts all the meaningful variables of the system. Its application range has been recently extended to include accidental conditions, in particular the so-called loss of coolant accidents (LOCA). In order to make realistic predictions, the conditions in the rod environment have been taken into account since they represent the boundary conditions with which the differential equations describing the fuel phenomena are solved. Without going into the details of the thermal-hydraulic modeling, which is the task of the specific codes, a simplified description of the conditions in the cooling channel during a LOCA event has been developed and incorporated as a subroutine of DIONISIO. This has led to an improvement of the fuel behavior simulation, which is evidenced by the considerable number of comparisons with experiments carried out, many of them reported in this paper. Moreover, this work describes a model of high temperature capture and release of hydrogen in the nuclear fuel cladding, in scenarios typical of LOCA events. The corresponding computational model is being separately tested and will be next included in the DIONISIO thermal-hydraulic module.
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April 2019
Research-Article
Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code
Martín Lemes,
Martín Lemes
Sección Códigos y Modelos,
Gerencia Ciclo del Combustible Nuclear,
Comisión Nacional de Energía Atómica,
Avenida General Paz 1499,
San Martín,
Provincia de Buenos Aires 1650, Argentina
e-mail: lemes@cnea.gov.ar
Gerencia Ciclo del Combustible Nuclear,
Comisión Nacional de Energía Atómica,
Avenida General Paz 1499,
San Martín,
Provincia de Buenos Aires 1650, Argentina
e-mail: lemes@cnea.gov.ar
Search for other works by this author on:
Alicia Denis,
Alicia Denis
Sección Códigos y Modelos,
Gerencia Ciclo del Combustible Nuclear,
Comisión Nacional de Energía Atómica,
Avenida General Paz 1499,
San Martín,
Provincia de Buenos Aires 1650, Argentina
e-mail: denis@cnea.gov.ar
Gerencia Ciclo del Combustible Nuclear,
Comisión Nacional de Energía Atómica,
Avenida General Paz 1499,
San Martín,
Provincia de Buenos Aires 1650, Argentina
e-mail: denis@cnea.gov.ar
Search for other works by this author on:
Alejandro Soba
Alejandro Soba
Sección Códigos y Modelos,
Gerencia Ciclo del Combustible Nuclear,
Comisión Nacional de Energía Atómica,
San Martín,
Provincia de Buenos Aires 1650, Argentina
e-mail: soba@cnea.gov.ar
Gerencia Ciclo del Combustible Nuclear,
Comisión Nacional de Energía Atómica,
Avenida General Paz 1499
,San Martín,
Provincia de Buenos Aires 1650, Argentina
e-mail: soba@cnea.gov.ar
Search for other works by this author on:
Martín Lemes
Sección Códigos y Modelos,
Gerencia Ciclo del Combustible Nuclear,
Comisión Nacional de Energía Atómica,
Avenida General Paz 1499,
San Martín,
Provincia de Buenos Aires 1650, Argentina
e-mail: lemes@cnea.gov.ar
Gerencia Ciclo del Combustible Nuclear,
Comisión Nacional de Energía Atómica,
Avenida General Paz 1499,
San Martín,
Provincia de Buenos Aires 1650, Argentina
e-mail: lemes@cnea.gov.ar
Alicia Denis
Sección Códigos y Modelos,
Gerencia Ciclo del Combustible Nuclear,
Comisión Nacional de Energía Atómica,
Avenida General Paz 1499,
San Martín,
Provincia de Buenos Aires 1650, Argentina
e-mail: denis@cnea.gov.ar
Gerencia Ciclo del Combustible Nuclear,
Comisión Nacional de Energía Atómica,
Avenida General Paz 1499,
San Martín,
Provincia de Buenos Aires 1650, Argentina
e-mail: denis@cnea.gov.ar
Alejandro Soba
Sección Códigos y Modelos,
Gerencia Ciclo del Combustible Nuclear,
Comisión Nacional de Energía Atómica,
San Martín,
Provincia de Buenos Aires 1650, Argentina
e-mail: soba@cnea.gov.ar
Gerencia Ciclo del Combustible Nuclear,
Comisión Nacional de Energía Atómica,
Avenida General Paz 1499
,San Martín,
Provincia de Buenos Aires 1650, Argentina
e-mail: soba@cnea.gov.ar
Manuscript received August 27, 2018; final manuscript received January 17, 2019; published online March 15, 2019. Assoc. Editor: Fidelma Di Lemma.This work was prepared while under employment by the Government of Argentina as part of the official duties of the author(s) indicated above, as such copyright is owned by that Government, which reserves its own copyright under national law.
ASME J of Nuclear Rad Sci. Apr 2019, 5(2): 020903 (11 pages)
Published Online: March 15, 2019
Article history
Received:
August 27, 2018
Revised:
January 17, 2019
Citation
Lemes, M., Denis, A., and Soba, A. (March 15, 2019). "Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code." ASME. ASME J of Nuclear Rad Sci. April 2019; 5(2): 020903. https://doi.org/10.1115/1.4042705
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