Published 1978 | Version v1
Book

Probability of failure of a reactor pressure-tube in case of loss of coolant accident

Creators

  • 1. Polytechnic Inst. of Milan, Italy

Description

The reliability of a Zr-2 pressure-tube to be installed in a D2O-moderated BLWR is evaluated for the transient following LOCA. Reference is made to regions of pressure-tube wall where end effects and mechanical constraints have a negligible influence. Plastic instability is selected, as the criterion of failure. Overall reliability is the conditional probability (assuming the failure criterion and given a sample of experimental data) that applied stress does not exceed allowable strength in anyway. During LOCA pressure and temperature transients are represented in terms of stochastic processes non-stationary in time. The two processes are postulated statistically independent and their structure is defined according to a model of cumulated effects. On the other hand, since there is the need of considering all possible locations along the tube, mechanical properties and loads are described by means of stochastic processes supposedly stationary in space. The problem of stress vs. strength interference which ensues is simplified through the identification of a critical time instant. Then, overall reliability can be reduced to the calculation of space reliability. In an idealistic two-dimensional case, reliability is approximated by the probability of (zero-) level crossing of the sum of a number of stochastic processes. Finally, the concept of bayesian reliability may be established and a sample of new data (on material properties) can be worked out to calculate posterior distributions

Additional details

Publishing Information

Publisher
American Nuclear Society, Inc.
Imprint Place
La Grange Park, IL
Imprint Title
Probabilistic analysis of nuclear reactor safety
Journal Page Range
p. III.9.1-III.9.12.

Conference

Title
Probabilistic analysis of nuclear reactor safety.
Dates
8 - 10 May 1978.
Place
Los Angeles, CA, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10487484
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CIRENE REACTOR; LOSS OF COOLANT; PRESSURE TUBES; PROBABILITY; RELIABILITY; RUPTURES
Descriptors DEC
ACCIDENTS; FAILURES; HEAVY WATER MODERATED REACTORS; HWLWR TYPE REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS