In a nuclear reactor core there are fuel assemblies with different age (i.e. how long the assembly has been in the core) and burnup (i.e. how much energy that has been extracted from the assembly). The fresh assemblies have higher reactivity, which means they generate more thermal power, and therefore need a higher coolant flow rate than the older assemblies. In order to redistribute the coolant flow from the older assemblies to the fresher assemblies, the core can be divided into different throttling zones. The older assemblies are placed in the periphery of the core which has higher throttling, while the fresher assemblies are placed in the central parts of the core which has lower throttling. This type of throttling is done in the core inlet. However, there is also an opportunity to throttle the flow into each separate fuel assembly, which is done in the bottom nozzle of the assembly. This type of throttling is usually constant during the whole time the assembly is in the core and is specific for the assembly type, which means that it does not contribute to the redistribution of coolant flow from older to fresher assemblies. In this project, so called variable throttling was studied. This means that the throttling of each assembly is increased after the assembly has been in the reactor core for a specific time (e.g. one or two years) and the need of coolant flow hence has decreased. By doing this, while also decreasing the total coolant flow rate through the core, the amount of void (steam) in the core increases but enough coolant flow is supplied to the fresher assemblies due to the increased redistribution of the flow. An increased amount of void leads to a shift of the neutron spectrum to higher energies (“hardening” of the spectrum), which in turn leads to better breeding. Better breeding means that more fissile material, mainly Pu-239, is produced in the core during operation. A lower enrichment can therefore possibly be used, which would reduce the fuel costs. The results show that, by implementing variable throttling, the breeding is improved and the relevant safety requirements are also fulfilled. According to the calculations, the enrichment in the fresh fuel could possibly be lowered with up to 0.068 weight percent, which means that the fuel costs would be reduced with up to approximately 8 MSEK per fuel cycle.

Examensarbetet behandlar problematik som uppstår vid härdsmältningsförlopp i en kärnkraftsreaktor av typen kokvattensreaktor. Resultatet ska användas som riktlinjer till strategier som utvecklas av Severe Accident Management Guidelines (SAMG) där arbetets uppdrag är ett delmoment i framtagning av strategier för att bemästra de olika fenomen som uppstår vid härdsmälta.   Syftet med arbetet är att undersöka begränsningar för att bevara reaktortanken intakt vid haveri, genom att undersöka den minsta mängd vatten som behövs för att undvika tankgenomsmältning. Undersöka fallen som leder till härdsmälta och gruppera dem efter händelsesekvenser. Undersöka metall/vatten-reaktionen som uppstår då härden blir över 800°C och undersök om fallen kan grupperas i händelsesekvenser.  Metoder som används i arbetet är PSA-dokumentation, händelseutvecklingsträd, teoretiska beräkningar och MAAPv5.03. Resultatet beskriver att grupperingar av fallen som slutar i härdsmälta och grupperingar av metall/vatten-reaktionen hos de olika fallen kan genomföras. Resultatet beskriver även ett minsta flöde som kan föras in i reaktortanken för att hindra tankgenomsmältning och flöden upp till 100 kg/s så det finns resultat för olika flöden beroende på vilka kylmedel som är tillgängliga.  Slutsatsen av arbetet är att fall kan grupperas efter händelsesekvenser och påverkan hos metall/vattenreaktion, grupperingarna sparar tid vid ett haveriförlopp. I varje grupp kunde det svåraste fallet beräknas för minsta flöde för att klara tankgenomsmältning och flöden upp till 100 kg/s.  Framtida arbeten bör undersöka trycket och vätgasen som skapas vid vatteninmatning samt dess påverkan på reaktorinneslutningen. / The master thesis deals with problems that arise during nuclear meltdown in a nuclear powerplant of the type boiling water reactor. The work will be used as guidelines for strategies developed by Severe Accident Management Guidelines (SAMG), this master thesis is a sub-element in the development of strategies for mastering the various phenomena that arise during a meltdown.  The purpose of the work is to investigate limitations for maintaining the reactor tank intact during the meltdown by, examining the minimum amount of water needed to avoid the meltdown getting through the reactor tank. Examining the cases that lead to meltdown and group them according to the event sequences. Examine the metal/water-reaction that occurs when the core becomes over 800°C and examine if the cases can be grouped into event sequences.  Methods used in the master thesis is PSA-analysis, event development threes, theoretical calculations and MAAPv5.03.  The result describes the groupings of the cases ending in meltdown and the groupings of the metal/water-reaction of the various cases. The result also describes a minimum flow that is required to prevent meltdown of getting through the reactor tank and flow up to a 100 kg/s.  The conclusion of the master thesis is that cases can be grouped according to event sequences and the influence of the metal/water-reaction, the groupings save time in the event of a breakdown. In each group the most difficult case was calculated so that the lowest flow to prevent the meltdown from getting through the reactor tank was presented among with different flows up to 100 kg/s. Future work should investigate the pressure and hydrogen gas created by the water input and its influence on the reactor inclusion.