Published 1987 | Version v1
Book Metadata-only

Fragility assessment of containment tangential shear failure

Creators

  • 1. Brookhaven National Lab., Upton, NY (USA). Dept. of Nuclear Energy
  • 2. Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Reactor Regulation

Description

This paper presents the fragility assessment of the reinforced concrete containment of the Indian Point-3 reactor with respect to the tangential shear failure. The tangential shear limit state is described in detail. The variations of material strengths such as the concrete compressive strength and reinforcement yield strength are included in the fragility analysis by using the Latin hypercube sampling technique. (orig./HP)

Additional details

Publishing Information

Publisher
Balkema.
Imprint Place
Rotterdam (Netherlands)
ISBN
90-6191-774-3
Imprint Title
Transactions of the 9th international conference on structural mechanics in reactor technology. Vol. M
Imprint Pagination
497 p.
Journal Page Range
p. 237-242.

Conference

Title
9. biennial international conference on structural mechanics in reactor technology (SMIRT-9).
Dates
17-21 Aug 1987.
Place
Lausanne (Switzerland).

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
19033160
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPRESSION STRENGTH; CONTAINMENT; FAILURES; INDIAN POINT-3 REACTOR; PROBABILITY; REINFORCED CONCRETE; RISK ASSESSMENT; SHEAR PROPERTIES
Descriptors DEC
BUILDING MATERIALS; COMPOSITE MATERIALS; CONCRETES; ENRICHED URANIUM REACTORS; MATERIALS; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; REINFORCED MATERIALS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS