Assessment of FEMAXI and TESPA-ROD codes for modelling of BDBA in RBMK-1500
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A. Jusevičiu-tė
Abstract
Processes occurring during the reactor operation and accidents change the thermal, chemical and other properties in nuclear fuel rods. This paper describes the processes in the nuclear fuel rods and tools for simulation at these processes. Fuel rods used at Ignalina NPP were simulated with FEMAXI-V (Japan) and TESPA-ROD (Germany) codes. Developed models were employed for the analysis of processes in fuel rods in case of large LOCA Beyond Design Basis Accident (BDBA). The developed models and results of the analysis are presented in this paper.
Kurzfassung
Prozesse, die während des Reaktorbetriebes und bei Störfällen stattfinden, ändern die thermischen, chemischen und anderen Eigenschaften in Brennelementen. Dieser Beitrag beschreibt die Prozesse in den Brennelementen und Tools für die Simulation dieser Prozesse. Die im Kernkraftwerk Ignalina eingesetzten Brennelemente wurden mit FEMAXI-V (Japan) und TESPA-ROD (Deutschland) Codes simuliert. Die entwickelten Modelle wurden für die Analyse von Prozessen in Brennelementen unter Annahme eines Kühlmittelverluststörfalls für auslegungsüberschreitende Ereignisse verwendet. Die entwickelten Modelle und Ergebnisse der Analyse werden in diesem Beitrag vorgestellt.
References
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© 2008, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Application of the HN method to radiative heat transfer for a non-conservative slab
- Application of the spectral Green's function method for numerically solving discrete ordinates problems in cylindrical geometry
- Chebyshev polynomial (TN) approximation to neutron transport theory and application to the critical slab problem
- Spherical albedo problem for isotropic scattering
- The slab albedo and criticality problem for the quadratic scattering kernel with the HN method
- An analytical solution for the time-dependent SN transport equation in a slab
- Deterministic calculation of grey Dancoff factors in cluster cells with cylindrical outer boundaries
- New calculations of excitation functions of some positron emitting and single photon emitting radioisotopes
- Prediction of the time-dependent failure rate for normally operating components taking into account the operational history
- Assessment of FEMAXI and TESPA-ROD codes for modelling of BDBA in RBMK-1500
- A study on the neutronic performance of the ARIES-RS fusion reactor with various coolants bearing nuclear fuel
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Application of the HN method to radiative heat transfer for a non-conservative slab
- Application of the spectral Green's function method for numerically solving discrete ordinates problems in cylindrical geometry
- Chebyshev polynomial (TN) approximation to neutron transport theory and application to the critical slab problem
- Spherical albedo problem for isotropic scattering
- The slab albedo and criticality problem for the quadratic scattering kernel with the HN method
- An analytical solution for the time-dependent SN transport equation in a slab
- Deterministic calculation of grey Dancoff factors in cluster cells with cylindrical outer boundaries
- New calculations of excitation functions of some positron emitting and single photon emitting radioisotopes
- Prediction of the time-dependent failure rate for normally operating components taking into account the operational history
- Assessment of FEMAXI and TESPA-ROD codes for modelling of BDBA in RBMK-1500
- A study on the neutronic performance of the ARIES-RS fusion reactor with various coolants bearing nuclear fuel
