Abstract
Spent fuel production is one of the main problems of nuclear power plants that should be managed properly considering the strategy of each country. Today, in most of nuclear power owner countries, the interim storage has been selected as the temporary solution of spent fuel management because of absence of deep geological repositories and no tendency for reprocessing. On the other side, considering the merits of storage in dual purpose casks based on dry storage, this method was chosen for interim storage. By taking into account that the only operating reactor of Iran is of Water-Water Energetic Reactor (WWER)-1000 type, proposed TK-13 cask by Russia which is the manufacturer of these types of reactors has been considered. In this study, the calculation of basket holding spent fuel assembly criticality of this cask has been analyzed for two modes of fresh and spent fuel by ORIGEN2.1 and MCNPX2.6 nuclear codes. The criterion of the nuclear criticality safety for effective multiplication factor (keff) should be 0.95 and 0.98 for many ordinary and accident conditions, respectively. Therefore, the results show that a cylindrical basket with 66 cm diameter and 28 cm pitch with internal holding basket made of borated steel with 0.1% borate and steel free from borate would meet the criticality of cask, respectively.
Kurzfassung
Der Umgang mit abgebrannten Brennelementen ist eines der Hauptprobleme bei Kernkraftwerken, das in jedem Land mit kerntechnischen Anlagen in geeigneter Art und Weise gemanagt werden muss. In den meisten dieser Länder wurde aufgrund fehlender geeigneter geologischer Tiefenformationen bzw. entsprechender Wiederaufarbeitungsanlagen die Zwischenlagerung als zeitlich begrenzte Lösung für die Aufbewahrung von abgebrannten Brennelementen gewählt. Für trockene Zwischenlagerung wurde die Aufbewahrung unter Verwendung von entsprechenden Lagerbehältern gewählt. Unter Berücksichtigung, dass der einzige in Betrieb befindliche Reaktor im Iran vom Typ WWER-1000 ist, wurde der von Russland vorgeschlagene und für die Brennelemente dieses Reaktortyps hergestellte Behälter TK-13 betrachtet. In dieser Studie wurde die Berechnung der Kritikalität von Brennelementen in Behältertragkörben vorgenommen. Die Analysen wurden sowohl für frische als auch abgebrannte Brennelemente unter Verwendung von ORIGEN2.1- und MCNPX2.6-Rechencodes durchgeführt. Als Kriterium für die Kritikalitätssicherheit diente der effektive Multiplikationsfaktor (keff) 0.95 bzw. 0.98 für normale Betriebs- bzw. Störfallbedingungen. Die Ergebnisse zeigen, dass ein Zylinderbehälter mit 66 cm Durchmesser und 28 cm Tragekorb aus boriertem Stahl mit 0.1% boriertem und borfreiem Stahl die Kritikalitätskriterien erfüllen würde.
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