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Additional resources for Accid. Anal. - Nuclear Powerplants with PWRs
Aspects (f) and partially (g) are dealt with in Sections 16 and 17, respectively. As already emphasized several times, the selection of acceptance criteria and consequently also the selection of conservative conditions differs considerably depending on the safety aspect under consideration. Generally, different calculations have to be performed for an analysis of different aspects of the accident. The relevant acceptance criteria typically corresponding to the safety aspects under consideration are Nos (6), (8) and (9–13) (Section 3).
2. SPECIFIC SUGGESTIONS FOR ANALYSIS The radioactivity release to the environment depends on the following factors: — — — — — — Quantity of coolant released to the atmosphere; Primary coolant activity; Secondary coolant activity; Spiking of the iodine isotopes and the noble gases; Degradation of fuel rods due to high temperatures; Position of the tube rupture in the broken SG and the decontamination factor; — Initial power level of the plant. The radiological consequences of PRISE leakages are usually analysed in two sequential steps: (1) (2) System analysis using system thermohydraulic codes; Analysis of radiological consequences using the results of the thermohydraulic calculation as boundary conditions.
All LOCA events are classified as accidents. Loss of primary coolant into the secondary circuit, for example due to the rupture of the SG tubes, requires special consideration and is discussed separately in Section 11. LOCAs have various safety aspects leading to potential violation of the acceptance criteria, as follows: (a) (b) (c) (d) (e) 32 The high velocity stream of the escaping primary coolant generates jet forces and reaction forces (leading to pipe whip) that endanger other systems close to the ruptured pipe and containment internals.
Accid. Anal. - Nuclear Powerplants with PWRs