Analysis of processes in RBMK-1500 fuel rods during the operation, short and intermediate term storage
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T. Kaliatka
Abstract
Recently the reactors of both units of Ignalina NPP in Lithuania were shutdown for decommissioning (in 2004 and 2009). According to the design, the spent fuel should be returned for reprocessing to Russia. However, up to now, all assemblies of spent fuel are still stored in the spent fuel pools and in the dry storage facility on-site of the Ignalina NPP. Thus, the safety justification for short and intermediate term spent fuel assemblies storage in Ignalina NPP is very important. The most important barrier, preventing release of radioactivity from the fuel matrix to the environment is the fuel rod cladding. The condition (integrity) of cladding at the end of intermediate storage of spent fuel assemblies may be evaluated by simulating processes in fuel rods during the whole “life cycle” of the fuel assembly: beginning from the first loading into the reactor core, until the end of dry intermediate storage in special casks. This paper presents the modelling of processes in fuel rods during normal operation of fuel assemblies in reactor, short term wet storage in spent fuel pool and intermediate storage in dry cask. The analysis was performed using FEMAXI-6 integral code for the analysis of processes in fuel rod. The behaviour of thermal (pressure inside fuel rod, temperatures of fuel pellets and cladding, etc.) and mechanical (change of the gap between pellets and cladding, stresses and plastic deformation in fuel pellets and cladding, etc.) parameters were calculated. The analysis performed demonstrates the possibility to describe the state of the fuel rods after normal operation and short and intermediate term fuel storage.
Kurzfassung
Vor einiger Zeit wurden die Reaktoren der beiden Einheiten des Kernkraftwerks Ignalina in Litauen zum Zweck der Stilllegung abgeschaltet (2004 und 2009). Es war geplant, die abgebrannten Brennelemente zur Wiederaufarbeitung nach Russland zurückzuführen. Bisher befinden sich jedoch noch alle Brennelemente in Abklingbecken und in Trockenlagern auf dem Gelände des Kernkraftwerks Ignalina. Deshalb sind Sicherheitsbetrachtungen für die kurz- und mittelfristige Lagerung sehr wichtig. Die Hauptbarriere, die die Freisetzung von Radioaktivität aus den Brennelementen in die Umgebung verhindert ist die Umhüllung der Brennelemente. Der Zustand (Integrität) der Umhüllung am Ende der Zwischenlagerung der abgebrannten Brennelemente kann mit Hilfe der Simulation von Prozessen in den Brennelementen über den gesamten Lebenszyklus der Brennelementanordnung hinweg bewertet werden: angefangen von der ersten Beladung im Reaktorkern, bis zum Ende der trockenen Zwischenlagerung in speziellen Behältern. Dieser Beitrag beschreibt die Modellierung von Prozessen in Brennstäben während des normalen Betriebs der Brennelementanordnung im Reaktor, während der kurzfristigen Lagerung in Abklingbecken und während der trockenen Zwischenlagerung in speziellen Behältern. Die Analyse wurde mit FEMAXI-6 Integralcode durchgeführt. Das Verhalten der thermischen (Druck innerhalb des Brennstabs, Temperatur der Brennstoffpellets und der Umhüllung, usw.) und mechanischen (Änderung des Zwischenraums zwischen Brennstoffpellets und Brennstabhülle, Spannungen und plastische Verformung in Brennstoffpellets und Brennstabhülle, usw.) Parameter wurde berechnet. Die durchgeführte Untersuchung zeigt die Möglichkeit den Zustand der Brennstäbe nach Normalbetrieb und kurz- und mittelfristigen Lagerung zu beschreiben.
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© 2014, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Analysis of processes in RBMK-1500 fuel rods during the operation, short and intermediate term storage
- Can mechanical stresses noticeably influence the diffusion of hydrogen in zircaloy?
- Out-of-pile modelling of nuclear fuel elements for MTR type reactors – Part 1
- Experimental study of PHWR debris bed under boil-off condition
- Effectiveness of radial flow on rewetting of AHWR fuel cluster
- Radiotracers in performance evaluation of nuclear grade resins Amberlite IRN-78 and Purolite NRW-8000
- The production of 238–242Pu(n,γ)239–243Pu fissionable fluids in a fusion-fission hybrid reactor
- Theoretical study of deuteron induced reactions on 6,7Li, 9Be and 19F targets
- Upgrading of neutron radiography/tomography facility at research reactor
- Assessment of the radiological health damage costs of the Yeniköy and Kemerköy lignite-fired power plants in Muğla
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Analysis of processes in RBMK-1500 fuel rods during the operation, short and intermediate term storage
- Can mechanical stresses noticeably influence the diffusion of hydrogen in zircaloy?
- Out-of-pile modelling of nuclear fuel elements for MTR type reactors – Part 1
- Experimental study of PHWR debris bed under boil-off condition
- Effectiveness of radial flow on rewetting of AHWR fuel cluster
- Radiotracers in performance evaluation of nuclear grade resins Amberlite IRN-78 and Purolite NRW-8000
- The production of 238–242Pu(n,γ)239–243Pu fissionable fluids in a fusion-fission hybrid reactor
- Theoretical study of deuteron induced reactions on 6,7Li, 9Be and 19F targets
- Upgrading of neutron radiography/tomography facility at research reactor
- Assessment of the radiological health damage costs of the Yeniköy and Kemerköy lignite-fired power plants in Muğla
