Overview of plant specific source terms and their impact on risk
Description
Probabilistic risk assesment and safety assessment focuses on systems and measures to prevent core meltdown, and it integrates many aspects of design and operation. It provides mapping of initiating event, frequencies onto plant damage state and through plant systems analysis, utilizes fault tree and event tree logic models, may include 'external event' analysis such as fire, flood, wind, seismic events. Percent contribution of sequences to the core damage frequency are shown for the following plants, taken as examples ZION, EDISON, OCONEE 3, SEABROOK, SIZEWELL B, MILLSTONE 3, RINGHALS 2. The presentation includes comparison of the following initiating event frequencies: loss of off-site power; small LOCA; large LOCA, steam generator tube rupture; loss of feedwater; turbine trip; reactor trip. Consequence analysis deals with: dispersion and depletion of radioactivity in the atmosphere, health effects, factors in the off-site emergency plan analyzed with codes that address the weather conditions; provision of mapping of source terms; risk diagram for early fatalities and for latent cancer fatalities
Files
35052289.pdf
Files
(1.4 MB)
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Additional details
Publishing Information
- Imprint Title
- Light water reactor severe accident seminar. Seminar presentation manual
- Imprint Pagination
- 561 p.
- Journal Page Range
- [68 p.]
- Report number
- INIS-XA-N--139
Conference
- Title
- Light water reactor severe accident seminar
- Dates
- 16-18 May 1988
- Place
- Brussels (Belgium)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35052289
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EMERGENCY PLANS; EXCURSIONS; FAILURE MODE ANALYSIS; FAULT TREE ANALYSIS; HEALTH HAZARDS; LOSS OF COOLANT; LOSS OF FLOW; MELTDOWN; MILLSTONE-3 REACTOR; OCONEE-3 REACTOR; PROBABILISTIC ESTIMATION; REACTOR CORE DISRUPTION; RINGHALS-2 REACTOR; RISK ASSESSMENT; SAFETY ANALYSIS; SEABROOK-1 REACTOR; SIZEWELL-B REACTOR; SOURCE TERMS; TRANSIENT OVERPOWER ACCIDENTS; ZION-1 REACTOR
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; ENRICHED URANIUM REACTORS; HAZARDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Figs, tabs