Published 1985
| Version v1
Book
Quantification of containment response in a probabilistic risk assessment
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
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20045157
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALGORITHMS; COMBUSTION; CONTAINMENT; FAILURE MODE ANALYSIS; FAILURES; FISSION PRODUCT RELEASE; HYDROGEN; MATRICES; POWER REACTORS; PRESSURE DEPENDENCE; PROBABILITY; REACTOR ACCIDENTS; REACTOR SAFETY; RESPONSE FUNCTIONS; RISK ASSESSMENT
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; ELEMENTS; FUNCTIONS; NONMETALS; OXIDATION; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS