Main results of German risk study, Phase B, in the light of methodological problems
Description
The German Risk Study, Phase B, which has been performed for a 1,300 MWe KWU-type pressurized water reactor, is a level 2 probabilistic safety assessment (PSA). In the study, 32 initiating events have been considered. An expected plant damage state frequency of about 3x10-5 per year has been calculated. In a plant damage state core meltdown can only be prevented by means of accident management procedures. The probability is high (about 98%) that in a plant damage state the primary system will not be depressurized. Core meltdown under high system pressure would endanger the containment integrity immediately. In most plant damage states accident management procedures are possible which bring the plant in a safe state or, at least, reduce the pressure in the primary system before the pressure vessel fails. On a preliminary basis, a success probability of 99% for accident management procedures (secondary or primary side bleed and feed) has been estimated. This results in an expected core melt frequency of about 4x10-6 per year. The expected frequency of high pressure core meltdown is about 6x10-7 per year. Loads on, and failure modes of, the containment during a core melt accident as well as release fractions after containment failure have been analyzed. The study did, however, refrain from quantifying the probability of containment failure modes. A main uncertainty in this area is the probability of containment failure due to hydrogen burning. The results of the study point out, that the risk can be reduced significantly if containment failure due to hydrogen burning can be reliably prevented
Additional details
Publishing Information
- Imprint Title
- CSNI workshop on PSA applications and limitations. Proceedings
- Imprint Pagination
- 475 p.
- Journal Page Range
- p. 81-94.
- Report number
- NUREG/CP--0115
Conference
- Title
- Committee on the Safety of Nuclear Installations (CSNI) on Probabilistic Safety Assessment (PSA) applications and limitations.
- Dates
- 4-6 Sep 1990.
- Place
- Santa Fe, NM (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23008767
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AVAILABILITY; COMBUSTION; CONTAINMENT SYSTEMS; CORIUM; DYNAMIC LOADS; EMERGENCY PLANS; FAILURE MODE ANALYSIS; FAILURES; FREQUENCY ANALYSIS; HYDROGEN; KRYPTON; LOSS OF COOLANT; MELTDOWN; MITIGATION; PRESSURE VESSELS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; RADIOACTIVITY TRANSPORT; REACTOR ACCIDENTS; REACTOR CORE DISRUPTION; RISK ASSESSMENT; RUPTURES; SOURCE TERMS; STEAM GENERATORS; TRANSIENTS; TUBES; VENTILATION; XENON
- Descriptors DEC
- ACCIDENTS; BOILERS; CHEMICAL REACTIONS; CONTAINERS; CONTAINMENT; ELEMENTS; ENRICHED URANIUM REACTORS; NONMETALS; OXIDATION; POWER REACTORS; RARE GASES; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- SAND--90-2797; CONF-9009346--.