Dynamic event tree analysis with the SAS4A/SASSYS-1 safety analysis code

Author:

Jankovsky Zachary K.,Denman Matthew R.,Aldemir Tunc

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference53 articles.

1. A survey of dynamic methodologies for probabilistic safety assessment of nuclear power plants;Aldemir;Ann. Nucl. Energy,2013

2. A Benchmark Implementation of Two Dynamic Methodologies for the Reliability Modeling of Digital Instrumentation and Control Systems, NUREG/CR-6985;Aldemir,2009

3. A new uncertainty importance measure;Borgonovo;Reliab. Eng. Syst. Saf.,2007

4. Brunett, A., Grabaskas, D., Bucknor, M., 2014. dynamic methods for the assessment of passive system reliability. In: Proceedings of the International Conference on Probabilistic Safety Assessment and Management (PSAM 12), Honolulu, HI.

5. Bruske, S., Einerson, J., Hinton, M., Mackowiak, D., Stoffel, J., Tawfik, M., Weber, D., Wright, R., Brinsfield, W., Brogan, B., Mays, S., Trainer, J., vonHermann, J., Wood, P., Fauske, H., Henry, R., Madell, J., 1983. Clinch River Breeder Reactor Plant Probabilistic Risk Assessment Phase I: Main Report, EGG-EA-6162. Idaho National Engineering Laboratory, Idaho Falls Idaho, January.

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