Uncertainty quantification and propagation with probability boxes

Author:

Duran-Vinuesa L.,Cuervo D.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference43 articles.

1. USNRC, “10 CFR Part 50 - Domestic Licensing of Production and Utilization Facilities.” .

2. Safety Assessment and Verification for Nuclear Power Plants: Safety Guide,2001

3. Regulatory Guide 1.157 (Task RS 701-4), Best-Estimate Calculations of Emergency Core Cooling System Performance.,” p. 20.

4. Quantifying Reactor Safety Margins: Application of Code Scaling, Applicability, and Uncertainty Evaluation Methodology to a Large-Break, Loss-Of-Coolant-Accident;Boyack,1989

5. The Best Estimate Plus Uncertainty (BEPU) approach in licensing of current nuclear reactors;D'Auria;Nucl. Eng. Des.,2012

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