Published 1985 | Version v1
Book

Quantification of containment response in a probabilistic risk assessment

Creators

  • 1. Pickard, Lowe and Garrick, Inc., CA (USA)

Description

This lecture consists of four parts. They embody the principal aspects of the steps and analyses required to determine: The Plant Damage States; the C-Matrix; and the Release Categories. The four parts addressed are: I. A methodology for the probabilistic quantification of containment response. II. The analysis of containment failure pressure and quantification of uncertainty. III. A probabilistic analysis of containment failure due to hydrogen burning. IV. Determination of source terms and uncertainities. This lecture emphasis the quantification of uncertainties in containment response as a key ingredient of a PRA (Probabilistic risk assessment)

Additional details

Publishing Information

Publisher
Pickard, Lowe and Garrick Inc.
Imprint Place
Newport Beach, CA (USA)
Imprint Title
Nuclear power plant risk management
Imprint Pagination
vp.
Journal Page Range
vp.

Conference

Title
Nuclear power plant risk management course.
Dates
17-19 Jun 1985.
Place
Washington, DC (USA).

INIS