'Containment failure' presentation slideshows

615 views • 42 slides

State-of-the-Art Reactor Consequence Analyses (SOARCA) Project Accident Analysis

State-of-the-Art Reactor Consequence Analyses (SOARCA) Project Accident Analysis. Presented at the USNRC 20 th Regulatory Information Conference Washington, DC March 11, 2008 Randall Gauntt, Sandia National Laboratories Charles Tinkler, USNRC.

495 views • 29 slides

An Approach to Evaluation of Uncertainties in Level 2 PSAs

An Approach to Evaluation of Uncertainties in Level 2 PSAs. T. Ishigami, J. Ishikawa, K. Shintani, M. Mayumi and K. Muramatsu Japan Atomic Energy Research Institute OECD/NEA/CSNI/WGRISK Workshop, Cologne, March 29 - 31, 2004. Introduction. Background

318 views • 19 slides

Outline

201 views • 19 slides

Risk Assessment of NPP Level2 PSA

337 views • 16 slides

Risk Assessment of NPP Level1 PSA

Risk Assessment of NPP Level1 PSA. 2011 6.10 JNES-VARANS Review Meeting. Contents. 1. Overview of PSA 2. Level1 PSA Methodology - Initiating Events - Event Tree Analysis - Fault Tree Analysis - Quantification of Plant Risks. 1. Overview of PSA - What is PSA? -.

331 views • 9 slides