Probabilistic analysis on the failure of reactivity control for the PWR
Author:
Publisher
IOP Publishing
Subject
General Physics and Astronomy
Link
http://stacks.iop.org/1742-6596/962/i=1/a=012046/pdf
Reference15 articles.
1. A combined deterministic and probabilistic procedure for safety assessment of beyond design basis accidents in nuclear power plant: Application to ECCS performance assessment for design basis LOCA redefinition
2. A survey of dynamic methodologies for probabilistic safety assessment of nuclear power plants
3. AP1000 passive core cooling system pre-operational tests procedure definition and simulation by means of Relap5 Mod. 3.3 computer code
4. Performance evaluating of the AP1000 passive safety systems for mitigation of small break loss of coolant accident using risk assessment tool-II software
5. Twofold application of nanofluids as the primary coolant and reactivity controller in a PWR reactor: Case study VVER-1000 in normal operation
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1. The evaluation of fundamental safety function and defence in depth of AP1000 using probabilistic analysis;AIP Conference Proceedings;2024
2. Probabilistic safety Analysis for Assessing the Failure of Heat Removal Control of AP1000;Journal of Physics: Conference Series;2019-04
3. The assessment of the radioactive releases from the confinement structure of AP1000 by probabilistic safety analysis;AIP Conference Proceedings;2019
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