A complex study on the reliability assessment of the containment of a PWR. I
Creators
- 1. Gesellschaft fuer Reaktorsicherheit m.b.H. (GRS), Garching (Germany, F.R.)
Description
For evaluation of the reliability of the safety enclosure in the case of accidents the time-dependent loads by internal pressure and temperature on the spheric steel containment and the correspondent probabilities had to be calculated. Of the spectrum of possible accidents, e.g. large LOCA which leads to a maximum pressure of approximately 4.7 bar, working of all safety systems presumed, small LOCA or rupture of a primary steam pipe, only those have been selected which result in a considerable increase of internal pressure in the safety containment. Technical data and accident event sequences describing the system analysed were taken from the PWR Biblis B, which at this time is typical for the PWR-line construction in the FRG. The computer code ZOCO VI was used to calculate pressure buildup for the different event sequences. The probability of certain event sequences leading to an accident has been calculated by multiplication of probabilities P1 X P2 X P3 X P4. The values have been determined by fault tree analysis of the different systems. (Auth.)
Additional details
Additional titles
- Subtitle (English)
- Magnitude and probability of internal load behaviour
Publishing Information
- Publisher
- North-Holland.
- Imprint Place
- Amsterdam, Netherlands
- ISBN
- 0 444 85062 7
- Imprint Title
- Structural mechanics in reactor technology
- Journal Page Range
- v. J(a) p. J1/10 1-12.
Conference
- Title
- 4. international conference on structural mechanics in reactor technology.
- Dates
- 15 - 19 Aug 1977.
- Place
- San Francisco, USA.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 10441806
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BIBLIS-B REACTOR; CONTAINMENT SYSTEMS; FAULT TREE ANALYSIS; LOSS OF COOLANT; PROBABILITY; RELIABILITY; SPHERICAL CONFIGURATION; STEELS; STRESSES; Z CODES
- Descriptors DEC
- ACCIDENTS; ALLOYS; CARBON ADDITIONS; COMPUTER CODES; CONFIGURATION; CONTAINMENT; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS