Tervetullut oppikirja monikulttuurisesta hoitotyöstä

Kirjallisuusarvostelu

Miesten talot ja naisten kodit

Kirjallisuusarvostelu

Seminaareja, naisia, keskusteluja

Kirjallisuusarvostelu

Sosiaalisen tuen sukupuoliparadoksit

Kirjallisuusarvostelu

Meistä ja heistä

Kirja-arvio

Naisten aika, paikka ja politiikka

Kirjallisuusarvostelu

Roolista, kokemuksesta ja naiseudesta

Kirjallisuusarvostelu

APROS model validation in case of fast transients in a boiling water reactor

This Master´s thesis investigates the performance of the Olkiluoto 1 and 2 APROS model in case of fast transients. The thesis includes a general description of the Olkiluoto 1 and 2 nuclear power plants and of the most important safety systems. The theoretical background of the APROS code as well as the scope and the content of the Olkiluoto 1 and 2 APROS model are also described. The event sequences of the anticipated operation transients considered in the thesis are presented in detail as they will form the basis for the analysis of the APROS calculation results. The calculated fast operational transient situations comprise loss-of-load cases and two cases related to a inadvertent closure of one main steam isolation valve. As part of the thesis work, the inaccurate initial data values found in the original 1-D reactor core model were corrected. The input data needed for the creation of a more accurate 3-D core model were defined. The analysis of the APROS calculation results showed that while the main results were in good accordance with the measured plant data, also differences were detected. These differences were found to be caused by deficiencies and uncertainties related to the calculation model. According to the results the reactor core and the feedwater systems cause most of the differences between the calculated and measured values. Based on these findings, it will be possible to develop the APROS model further to make it a reliable and accurate tool for the analysis of the operational transients and possible plant modifications.